Molten salt reactor

ABSTRACT

Systems and methods for providing and using molten salt reactors are described. While the systems can include any suitable component, in some cases, they include a graphite reactor core defining an internal space that houses one or more fuel wedges, where each wedge defines one or more fuel channels that extend from a first end to a second end of the wedge. In some cases, one or more of the fuel wedges comprise multiple wedge sections that are coupled together end to end and/or in any other suitable manner. In some cases, one or more alignment pins also extend between two sections of a fuel wedge to align the sections. In some cases, one or more seals are also disposed between two sections of a fuel wedge. Thus, in some cases, the reactor core can be relatively long (e.g., to be a pipeline reactor). Other implementations are also described.

CROSS-REFERENCE TO RELATED APPLICATION

This is a divisional of U.S. application Ser. No. 15/448,789, filed Mar.3, 2017, and entitled MOLTEN SALT REACTOR, which is acontinuation-in-part of U.S. application Ser. No. 14/859,100, filed Sep.18, 2015, and entitled SYSTEMS AND METHODS FOR PROVIDING A MOLTEN SALTREACTOR, the entire disclosures of which are hereby incorporated byreference.

FIELD OF THE INVENTION

The present invention relates to molten salt reactors. Moreparticularly, some implementations of the described invention relate tosystems and methods for providing and using molten salt reactors. Whilethe described systems can include any suitable component, in someimplementations, they include a graphite reactor core defining aninternal space that houses one or more fuel wedges, where each wedgedefines one or more fuel channels that extend from a first end to asecond end of the wedge. In some implementations, one or more of thefuel wedges comprise multiple wedge sections that are coupled togetherend to end and/or in any other suitable manner. Thus, in some cases, thereactor core can be relatively long. Additionally, in someimplementations, one or more sections of the fuel wedges and/or parts ofother reactor components are configured to be replaced relativelyeasily.

BACKGROUND AND RELATED ART

The need for electrical energy across the world appears to be evergrowing. In this regard, electricity for power grids across the world isgenerated through a wide variety of methods. In one example, coal,natural gas, petroleum, another fossil fuel, wood, waste, and/or one ormore other fuel sources are burned to create heat, which is then used toturn a turbine (e.g., via pressure applied to the turbine by steam thatis created, and/or by air that is expanded, by the heat) and ultimatelyto turn an electrical generator.

In another example, wind or water is used to create electricity as suchmedia move past (or otherwise interact with) a generator. For instance,water passing through a hydroelectric dam, water passing a water wheel,air passing a wind turbine, and tidal water passing a tidal energyconverter have each been found to be effective methods for generatingelectricity.

In still other examples, sunlight (e.g., via solar cells, solar thermalenergy generators) and/or geothermal energy (e.g., via vapor-dominatedreservoirs, liquid-dominated reservoirs, enhanced geothermal systems,geothermal heat pumps, etc.) are used to generate electricity. Moreover,in still another example, nuclear energy is used to generateelectricity. In this regard, uranium or another fissionable material istypically used to generate heat that converts water to steam, which, inturn, rotates one or more turbines that are coupled to one or moreelectric generators.

Although many conventional methods for generating electricity haveproven to be useful, such methods are not necessarily without theirshortcomings. For instance, some methods that generate electricity byburning fossil fuels, also produce relatively large amounts of pollutionand carbon dioxide gas, while depleting the Earth's limited naturalresources. Additionally, some methods for generating electricity viasolar-power and/or wind-power systems are only able to generateelectricity when they are exposed to a sufficient amount of sunlightand/or wind—factors that are not necessarily available 24 hours a dayand 365 days a year. Moreover, as some geothermal and hydroelectricpower systems rely upon, and are limited by, the natural conditions onwhich such systems rely, many such systems are optimally (and sometimesonly) placed in specific locations (e.g., at tectonic plate boundaries,rivers, reservoirs, coast lines, etc.) that have the requisiteconditions. Furthermore, some nuclear power plants also haveshortcomings, which can include potential environmental damageassociated with potential meltdowns, accident, uranium mining, andnuclear waste generated by the power plants.

Thus, while systems and methods currently exist that are used togenerate electricity, challenges still exist, including those listedabove. Accordingly, it would be an improvement in the art to augment oreven replace current techniques with other techniques.

SUMMARY OF THE INVENTION

The present invention relates to molten salt reactors. Moreparticularly, some implementations of the described invention relate tosystems and methods for providing and using molten salt reactors. Whilethe described systems can include any suitable component, in someimplementations, they include a graphite reactor core defining aninternal space that houses one or more fuel wedges, where each wedgedefines one or more fuel channels that extend from a first end to asecond end of the wedge. In some implementations, one or more of thefuel wedges comprise multiple wedge sections that are coupled togetherend to end and/or in any other suitable manner. In some cases, one ormore alignment pins also extend between two sections of a fuel wedge toalign the sections. In some cases, one or more seals are also disposedbetween two sections of a fuel wedge. Thus, in some cases, the reactorcore can be relatively long. Additionally, in some implementations, oneor more sections of the wedges and/or parts of other reactor componentsare configured to be replaced relatively easily.

In accordance with some implementations, the described molten saltreactor includes a reactor core that is made from graphite and thatdefines an internal space. In some such implementations, a graphite fuelwedge is disposed in the internal space, with the fuel wedge definingone or more fuel channels that are configured to allow a fissionablefuel to flow from a first end to a second end of the fuel wedge.

Some implementations further include a molten salt reactor that includesa graphite reactor core that defines a tubular internal space. In somesuch implementations, a first fuel wedge defining a first set of fuelchannels and a second fuel wedge defining a second set of fuel channelsare disposed in the internal space. Additionally, in some suchimplementations, the first and second sets of fuel channels areconfigured to allow a fissionable fuel comprising a molten salt to flowfrom a first end of the internal space to a second end of the internalspace through the first and second set of fuel channels.

In yet other implementations, the described molten salt reactor includesa reactor core that is disposed in a reactor housing and that comprisesgraphite and defines multiple fuel channels that run between a first endand a second end of the reactor core. In some cases, the reactor corecomprises one or more fuel ingress ports (or inlets) and egress ports(or outlets), and the reactor core is rotatably received within thereactor housing such that the fuel ingress and egress ports areconfigured to become at least one of more occluded (e.g., eclipsed,closed, etc.) and less occluded (e.g., more open) as the reactor corerotates within the housing.

Additionally, some implementations include a molten salt reactor thatincludes a reactor core that is disposed in a reactor housing and thatcomprises graphite and defines an internal space with multiple fuelwedges being received within the internal space, wherein the fuel wedgeseach define a fuel channel that is configured to allow a fissionablefuel to flow from a first end to a second end of each of the wedges. Insome cases, a fuel pin rod is disposed between at least two of thewedges, with the fuel pin rod defining an internal fuel conduit.Additionally, in some cases, the reactor core further comprises a fuelingress port and a fuel egress port, and the reactor core is rotatablyreceived within the reactor housing such that the fuel ingress andegress ports are configured to become at least one of more occluded andless occluded as the reactor core rotates within the housing.

In still other implementations, in addition to (or in place of) rotatinga portion of the reactor core to regulate the flow of fuel through thereactor, one or more pumps are configured to increase, decrease, and/orotherwise regulate the rate at which fuel is forced through the reactor.Accordingly, in some such implementations, pumps are used to increaseand/or decrease the dwell time and/or flow rate of fuel within thereactor to increase and/or decrease a temperature of the fuel.

In yet other implementations, the described methods include a method forusing a molten salt reactor, where the method includes obtaining amolten salt reactor and flowing a fissionable fuel through one or morefuel channels in the reactor. While the salt reactor in suchimplementations can have any suitable characteristic, in some instances,it includes a graphite reactor core that defines an internal space andthat includes one or more fuel wedges in the internal space, where thefuel wedges each define one or more fuel channels that are configured toallow the fissionable fuel to flow from a first end to a second end ofthe reactor.

While the methods and processes of the present invention may beparticularly useful for generation of electricity, those skilled in theart will appreciate that the described systems and methods can be usedin a variety of different applications and in a variety of differentareas of manufacture. For instance, instead of comprising a generator,some implementations of the described systems and methods are configuredto provide heat to one or more buildings, stadiums, neighborhoods,and/or other structures and facilities.

In some other cases, the described systems are configured fordesalination and/or to distill water (e.g., to create drinking (orrelatively clean) water from salt water or another non-potable and/orpolluted water source). In still other cases, the described systems andmethods are configured to provide energy for use in: oil shale and oilsand production, molten pool thermal electric sterling motors, onshoreand offshore power plants, automobiles, trains, ships, submarines,airplanes, helicopters, space shuttles, off-planet applications (e.g.,on the moon), the production of hydrogen fuels, the production of biogas applications, locations where portable power stations are useful(e.g., by attaching the molten salt reactor to a trailer, a skid, avehicle, etc.), providing geothermal liquid enhancers, heating water foraqua culture, and/or for a wide variety of other suitable purposes.

These and other features and advantages of the present invention will beset forth or will become more fully apparent in the description thatfollows and in the appended claims. The features and advantages may berealized and obtained by means of the instruments and combinationsparticularly pointed out in the appended claims. Furthermore, thefeatures and advantages of the invention may be learned by the practiceof the invention or will be obvious from the description, as set forthhereinafter.

BRIEF DESCRIPTION OF THE DRAWINGS

In order that the manner in which the above-recited and other featuresand advantages of the present invention are obtained, a more particulardescription of the invention will be rendered by reference to specificembodiments thereof, which are illustrated in the appended drawings.Understanding that the drawings are not necessarily drawn to scale or inproper proportion, and that the drawings depict only typical embodimentsof the present invention and are not, therefore, to be considered aslimiting the scope of the invention, the present invention will bedescribed and explained with additional specificity and detail throughthe use of the accompanying drawings in which:

FIG. 1A illustrates a block diagram of a molten salt reactor system inaccordance with a representative embodiment of the invention;

FIG. 1B illustrates a perspective view of the molten salt reactor systemin accordance with a representative embodiment;

FIG. 1C illustrates a schematic view of the molten salt reactor systemin accordance with a representative embodiment;

FIG. 2A illustrates a cross-sectional view of a reactor core housing inaccordance with a representative embodiment;

FIG. 2B illustrates a top schematic view of the reactor core housing ina partially assembled representative embodiment;

FIG. 2C illustrates a cross-sectional view of the reactor core housingin accordance with a representative embodiment;

FIG. 3A illustrates a perspective view of a representative embodiment ofthe reactor core housing;

FIG. 3B illustrates a side view of a representative embodiment of thereactor core housing;

FIG. 3C illustrates a perspective view of a representative embodiment ofthe reactor;

FIG. 4A illustrates a perspective, exploded view of a reactor core inaccordance with a representative embodiment;

FIGS. 4B-4C each illustrate a cross-sectional view of the reactor core,in accordance with a representative embodiment, and wherein the reactorcore itself is configured to act as a moderator;

FIG. 4D illustrates, in accordance with a representative embodiment, across-sectional view of the reactor core, wherein the reactor corecomprises a cylindrical insert configured to function as an internalmoderator;

FIG. 4E illustrates a cross-sectional view of the reactor core inaccordance with a representative embodiment;

FIG. 4F illustrates, in accordance with a representative embodiment, across-sectional view through the reactor core, wherein the core includesmultiple fuel pin rods that are disposed between multiple fuel wedges;

FIG. 4G illustrates a cross-sectional view through the reactor core, thecore having multiple fuel wedges and a fuel pin rod in accordance with arepresentative embodiment;

FIG. 4H illustrates a cross-sectional view through the reactor core, thecore having multiple fuel wedges in accordance with a representativeembodiment;

FIG. 4I illustrates a cross-sectional view through the reactor core, thecore having multiple arc-shaped fuel wedges and the fuel pin rod inaccordance with a representative embodiment;

FIG. 4J illustrates a perspective, exploded view of the reactor core inaccordance with a representative embodiment;

FIG. 4K illustrates a cross-sectional view of the reactor core inaccordance with a representative embodiment;

FIG. 4L illustrates a cross-sectional view through a reactor core tube,the fuel pin rods, and the fuel wedges in accordance with arepresentative embodiment;

FIG. 4M illustrates a cross-sectional view through the reactor corehousing in accordance with a representative embodiment;

FIGS. 4N-4O each illustrate a cross-sectional view of a differentembodiment of fuel wedges for use in some embodiments of the reactorcore;

FIG. 5A illustrates a perspective view of a bottom reflector inaccordance with a representative embodiment;

FIG. 5B illustrates a top view of the bottom reflector in accordancewith a representative embodiment;

FIG. 5C illustrates a partial break-away view of the bottom reflector inaccordance with a representative embodiment;

FIG. 5D illustrates a side, cross-sectional view of the bottom reflectorin accordance with a representative embodiment;

FIG. 6A illustrates a perspective view of a top reflector in accordancewith a representative embodiment;

FIG. 6B illustrates a bottom view of the top reflector in accordancewith a representative embodiment;

FIG. 6C illustrates a partial break-away view of the top reflector inaccordance with a representative embodiment;

FIG. 6D illustrates a side, cross-sectional view of the top reflector inaccordance with a representative embodiment;

FIG. 7A illustrates a prospective view of a side reflector in accordancewith a representative embodiment;

FIG. 7B illustrates a front view of the side reflector in accordancewith a representative embodiment;

FIG. 7C illustrates a side view of the side reflector in accordance witha representative embodiment;

FIG. 8A illustrates a prospective view of a partially-assembled heatexchanger in accordance with a representative embodiment;

FIG. 8B illustrates a top view of the partially-assembled heat exchangerin accordance with a representative embodiment;

FIG. 8C illustrates a first cross-sectional view of the heat exchangerin accordance with a representative embodiment;

FIG. 8D illustrates a second cross-sectional view of the heat exchangerin accordance with a representative embodiment;

FIG. 8E illustrates a third cross-sectional view of the heat exchangerin accordance with a representative embodiment;

FIG. 9A illustrates a prospective view of a partially-assembled steamgenerator in accordance with a representative embodiment;

FIG. 9B illustrates a top view of the partially-assembled steamgenerator in accordance with a representative embodiment;

FIG. 9C illustrates a first cross-sectional view of the steam generatorin accordance with a representative embodiment;

FIG. 9D illustrates a second cross-sectional view of the steam generatorin accordance with a representative embodiment;

FIG. 9E illustrates a side view of the steam generator in accordancewith a representative embodiment;

FIG. 9F illustrates a side view of a fuel pin in accordance with arepresentative embodiment;

FIG. 10 illustrates a schematic view of the molten salt reactor systemin accordance with a representative embodiment of the invention;

FIG. 11A illustrates a perspective, schematic view of a fuel wedgecomprising multiple sections that are coupled together in accordancewith a representative embodiment;

FIG. 11B illustrates a plan view of an end face of a section of the fuelwedge in accordance with a representative embodiment;

FIG. 11C illustrates a side view of a section of the fuel wedge inaccordance with a representative embodiment;

FIGS. 11D-11F each illustrate a side, cross-sectional view of adifferent seal disposed between two sections of the fuel wedge inaccordance with representative embodiments;

FIGS. 11G-11H each illustrate a cross-sectional view through the reactorcore, wherein the core includes multiple alignment pins in accordancewith some representative embodiments;

FIG. 11I illustrates a cross-sectional view through the reactor core inaccordance with a representative embodiment;

FIGS. 11J-11K each illustrate a schematic view of the reactor inaccordance with some representative embodiments;

FIG. 11L illustrates a perspective, exploded view of the reactor core inaccordance with a representative embodiment;

FIG. 12 illustrates a representative system that provides a suitableoperating environment for use with some embodiments of the molten saltreactor system; and

FIG. 13 illustrates a representative embodiment of a networked systemthat provides a suitable operating environment for use with someembodiments of the molten salt reactor system.

DETAILED DESCRIPTION OF THE INVENTION

The present invention relates to molten salt reactors. Moreparticularly, some embodiments of the described invention relate tosystems and methods for providing and using molten salt reactors. Whilethe described systems can include any suitable component, in someembodiments, they include a graphite reactor core defining an internalspace that houses one or more fuel wedges, where each wedge defines oneor more fuel channels that extend from a first end to a second end ofthe wedge. In some embodiments, one or more of the fuel wedges comprisemultiple wedge sections that are coupled together end to end and/or inany other suitable manner. In some cases, one or more alignment pinsalso extend between two sections of a fuel wedge to align the sections.In some cases, one or more seals are also disposed between two sectionsof a fuel wedge. Thus, in some cases, the reactor core can be relativelylong. Additionally, in some embodiments, one or more sections of thewedges and/or parts of other reactor components are configured to bereplaced relatively easily.

The following disclosure is grouped into two subheadings, namely “MOLTENSALT REACTOR” and “REPRESENTATIVE OPERATING ENVIRONMENT.” Theutilization of the subheadings is for convenience of the reader only andis not to be construed as being limiting in any sense.

Molten Salt Reactor

While the described systems can comprise any suitable component, FIG. 1Ashows that in accordance with some representative embodiments thedescribed molten salt reactor system 10 optionally comprises one or moreheaters 15, reactors 20, heat exchangers 25, steam generators 30, and/orelectric generators 35. Additionally, while the described systems canfunction in any suitable manner, FIG. 1A shows that, in someembodiments, the heater 15 is configured to heat one or more fissionablefuel sources (not shown) and/or carrier mediums (not shown)(collectively, the “fuel”) into a molten state and to pass the moltenfuel to the reactor 20. In some embodiments, the reactor 20 isconfigured to function as a neutron moderator that is designed to reducethe speed of fast neutrons in the molten fuel and to convert suchneutrons into thermal neutrons that allow the fuel to sustain a nuclearchain reaction (or to be in a critical state), which further heats thefuel.

In accordance with some embodiments, FIGS. 1A-1C show that heated fuel(not shown) is cycled in a first fluid line 40 between the heatexchanger 25 and the reactor 20 such that as the fuel passes through theheat exchanger, heat from the heated fuel is optionally passed to a heattransfer medium (not shown) running through a second fluid line 45 thatis separate from the first fluid line. In some embodiments (as shown inFIGS. 1A-1C), the second fluid line 45 extends between the heatexchanger 25 and the steam generator 30 and/or any other suitablelocation.

In some such embodiments, the system is optionally configured to movethe heat transfer medium from the heat exchanger 25 (where the medium isheated), through the steam generator 30 (where heat from the heattransfer medium causes water in the steam generator to turn into steam),and the heat transfer medium is then returned to the heat exchanger(where the transfer medium is reheated). In accordance with someembodiments, FIG. 1A shows that steam from the steam generator 30 isoptionally directed to the electric generator 35 (e.g., via a third line50 and/or otherwise), where the steam is used to turn one or moreturbines to generate electricity.

To provide a better understanding of the described system 10, each ofthe aforementioned components is described below in more detail.

With respect to the heater 15, the heater can comprise any suitablecomponent that allows it to heat the fissionable fuel to a molten stateand to then pass the molten fuel to the reactor 20. Indeed, inaccordance with some embodiments, FIG. 1A shows the heater comprises acontainer 55, which is configured to hold the fuel, and a heat source 60that is configured to heat the fuel.

The container 55 can have any suitable characteristic that allows theheater 15 to function as intended. For instance, the container can: beany suitable size (e.g., hold a volume of fuel that is larger than,smaller than, and/or approximately equal in volume to an internal volumeof a reactor core in the reactor 20), be made of any suitable materials(e.g., comprise one or more nickel alloys, low-chromiumnickel-molybdenum alloys (such as HASTELLOY-N™), metals, cements,ceramics, synthetic materials, and/or any other suitable materials), andhave any suitable component (e.g., one or more drains that areconfigured to drain molten fuel to the reactor and/or another container,pumps that are configured to force the fuel to the reactor and/oranother suitable container, mixers that are configured to mix variouscomponents of the fissionable fuel, vents, valves, lids, seals,thermostats, fluid level sensors, fluid sensors, radiation sensors,sensors, fans, and/or other suitable components) that allows the heaterto function as intended. Indeed, in some embodiments, the containercomprises one or more agitators, shakers, orbital mixers, and/or othermixers that are capable of mixing the various components of the fuel asit is cracked.

With regards to the heat source 60, the heat source can comprise anysuitable heat source that is capable of converting (or cracking) one ormore components of the fuel to a molten state. Some examples of suitableheat sources include, but are not limited to, one or more burners,heating coils, heating elements, ovens, fires, solar heaters, and/orother suitable heat sources that are capable of liquefying the fuel. Theheat source may also use any suitable energy source to heat thecontainer 55 to a desired temperature. Some non-limiting examples ofsuch energy sources include fossil fuels, coal, electricity, wood,biomass, biofuel, and/or any other suitable source.

Once the fuel has been cracked, the fuel can be moved from the heater 15to the reactor 20 in any suitable manner. In one example, the fuel ispumped (e.g., via one or more pumps 22 (ceramic and/or any othersuitable pump), as shown in FIG. 1A) from the heater 15 to the reactor20. In another example, the fuel is allowed to drain into the reactorvia gravity. In still another example, a reactor core comprises a vacuumthat is configured to draw the fuel into the core (e.g., once a valve isopened).

In some embodiments, once the heater 15 has cracked the fuel and thefuel has gone critical in the reactor 20, the heater is no longer neededto maintain the fuel in a molten state. Accordingly, while the heater 15can have any suitable relationship with the reactor 20, in someembodiments, once the fuel has been cracked by the heater and beenintroduced into the reactor, the heater is disconnected from thereactor, a valve between the heater and the reactor is closed, and/orthe system 10 is otherwise modified such that fuel in the reactor doesnot flow back into the heater until desired (e.g., if and when the fuelstarts to cool and/or as the fuel is stored before being reintroducedinto the reactor). Thus, in some embodiments, the heater is used tostart and to restart (and/or to optimize) the system (e.g., when thesystem is started for the first time, after the system has been shutdown for maintenance, when the fuel falls below a desired temperaturebefore entering the reactor, and/or for any other reason).

With respect to the fuel, the fuel can comprise any suitable ingredientor ingredients that allow the fuel to be heated into a molten state andto go critical in the reactor 20. Indeed, as mentioned above, in someembodiments, the fuel comprises a fissionable fuel source and a carriermedium. Some examples of suitable fissionable fuel sources include, butare not limited to, U-233, thorium U-232, U-235, Th-232, Th-228, Th-230,Th-234, nuclear waste from a nuclear reactor (e.g., one or more lightwater, and/or other nuclear reactors), fuel un-cladded nuclear spentfuel rods, nuclear spent fuel rod pellets, Pu-239, UF₄-LiF, PuF₃, and/orany other suitable fissionable material and/or precursor to a suitablefissionable material. Indeed, in some embodiments, the fissionable fuelsource comprises U-232, U-233, and/or U-235. Additionally, in someembodiments, the fuel comprises one or more other atomic elements thatare configured to be mixed (e.g., homogeneously or otherwise) into thefuel.

The various components of the fissionable fuel source can be present inthe fuel at any suitable concentrations. Indeed, in some embodiments inwhich the fuel comprises U-232 and U-233, the two components arerespectively used at a molar ratio between about 100:1 and 1:100, or atany suitable subrange thereof. Indeed, in some embodiments, when thefuel is initially added to the reactor, the fuel respectively comprisesU-232 and U-233 at a molar ratio between about 6:1 and about 2:1 (e.g.,at a ratio of about 4:1) though other materials (e.g., atomic elementsand/or other suitable materials) can also be mixed therein.

With respect to the carrier medium, the fuel can comprise any suitablecarrier medium that allows the fuel to go critical in, and that is safefor use with, the reactor 20. Some examples of such carrier mediumsinclude, but are not limited to, KNO₃ (potassium nitrate), NaNO₃ (sodiumnitrate), ThF₄ (thorium fluoride), LiF (lithium fluoride), BeF₂(beryllium fluoride), FLiBe (a molten mixture of lithium fluoride andberyllium fluoride), FLiNaK (a metal salt mixture of LiF, NaF (sodiumfluoride), and/or KF (potassium fluoride)), and/or any other suitablesalt or salts. Indeed, in some embodiments, the carrier medium comprisespotassium nitrate and/or sodium nitrate. In some other embodiments, thecarrier medium comprises potassium fluoride and/or sodium fluoride alongwith one or more other high thermal salts that can become a homogenousatomic element blend in the fuel.

Where the carrier medium comprises more than one ingredient, the variousingredients can be present at any suitable concentration in the fuel.Indeed, in some embodiments, the two components (e.g., potassium nitrateand sodium nitrate, potassium fluoride and sodium fluoride, etc.) arerespectively used at a molar ratio between about 100:1 and 1:100, or atany suitable subrange thereof. In this regard, in some embodiments, thecarrier medium respectively comprises potassium nitrate and sodiumnitrate at a molar ratio between about 6:1 and about 0.5:1 (e.g., at aratio of about 1.5:1). In some embodiments, the fuel includes a mixtureof 60% potassium nitrate to 40% sodium nitrate, along with one or moreother homogenous salt blends.

Turning now to the reactor 20, the reactor can comprise any suitablecomponent and characteristic that allows the fuel to obtain and/orsustain a nuclear chain reaction by passing through the reactor. By wayof non-limiting illustration, FIGS. 2A-2B show that, in someembodiments, the reactor 20 optionally comprises one or more housings65, reactor cores 70, reflectors 75, fuel inlets 80, fuel outlets 85,reactor control mechanisms 90, and/or drains 95.

With regards to the housing 65, the housing can comprise any suitablecomponent or characteristic that allows the housing to contain thereactor core 70 and to prevent undesired amounts of neutrons and/orgamma radiation from escaping the housing. While the housing can furthercomprise any suitable component that allows it to substantially envelopethe reactor core, FIGS. 2A-3B show that, in some embodiments, thehousing 65 includes a container 100 having a cover 105 that isselectively removable and/or openable to provide access to the reactorcore 70, the reflectors 75, and/or any other suitable component. In somesuch embodiments, the housing 65 (as shown in FIGS. 2B-2C) furthercomprises one or more seals 110, which may include, but are not limitedto, one or more carbon seals, carbon ropes, carbon-containing materials,rubber seals, gaskets, positive seals, mating seals (or objects thatcome together to form a seal), and/or any other suitable seal and/orsealing material. Indeed, in some embodiments, FIG. 2C shows the seal110 between the cover 105 and the container 100 comprises one or morecarbon ropes 115.

The housing 65 can comprise any suitable material that allows it tofunction as intended. Indeed, in some embodiments, the housing comprisesone or more metals (e.g., lead, steel, iron, tungsten, nuclear grademetals, and/or any other suitable metals), alloys (e.g., one or morenickel alloys, low-chromium nickel-molybdenum alloys (e.g.,HASTELLOY-N™), nuclear grade alloys, and/or other suitable alloys),cements, types of nuclear gunnite, types of nuclear shotcretes, types ofmortar, types of reinforced cement, ceramics, synthetic materials,natural materials, polymers, nano-metals, plastics, hydrogen-basedmaterials, fiberglass, stone, and/or any other suitable materials. Insome embodiments, however, the housing comprises a low-chromiumnickel-molybdenum alloy, such as a HASTELLOY-N™ material. Additionally,in some embodiments, the housing further comprises one or more internaland/or external liners (e.g., lead, steel, ceramic, nano-composites,graphite, graphite foam, and/or plastic liners), a secondary containmenthousing (comprising the same materials as, or different materials than,the housing), and/or one or more reinforcement elements (e.g., steelrods, steel meshes, fiber reinforcements, composites, graphite foam,graphite metal composites, and/or any other suitable reinforcements).

Turning now to the reactor core 70, the core can comprise any suitablecomponent or characteristic that allows it to act as a moderator as thefuel passes through it, such that the core is able to help the fuelreach (and/or maintain) a critical state. Some non-limiting examples ofsuch elements include, a reactor core tube and one or more end caps,internal moderators, and/or diffusers.

With reference to the reactor core tube, the tube can comprise anysuitable characteristic that allows it to function as described herein.In this regard, the tube can be any suitable shape, including, withoutlimitation, being cylindrical, polygonal, cuboidal, symmetrical,asymmetrical, tubular, spherical, prism-shaped (e.g., hexagonal prismshaped, polygonal prism shaped, pentagonal prism shaped, cuboidal prismshaped, parallel-piped prism shaped, octagonal prism shaped, rectangularprism shaped, and/or any other suitable prism shape), and/or any othersuitable shape. By way of non-limiting illustration, FIG. 4A shows anembodiment in which the reactor core tube 120 is substantiallycylindrical and tubular in shape, having a first end 125 and a secondend 130 with an internal space 135 defined between the two ends.

The reactor core tube 120 can be any suitable size. Indeed, while thereactor core tube can be any suitable length, in some non-limitingembodiments, the tube has a length that is between about 0.05 meters (m)and about 150 m, or any length that falls in such range. In this regard,some embodiments comprise a reactor core tube having a length betweenabout 0.1 m and about 61 m. In still other embodiments, the reactor coretube has a length between about 0.2 m and about 31 m. In yet otherembodiments, the reactor core tube has a length between about 0.3 m andabout 2.5 m (e.g., between about 0.5 m and about 0.8 m). In otherembodiments, the reactor core tube has length that is even greater thanor shorter than the lengths set forth herein. In this regard, it will beunderstood that the reactor core tube's size may vary greatly, dependingon its particular use.

While the reactor core tube 120 can have any suitable width or diameter,in some embodiments, the tube has an inner diameter or width (or ID)that is between about 0.04 m and about 10 m, or any width/diameter thatfalls in such range. In this regard, some embodiments of the reactorcore tube comprise an ID that is between about 0.2 m and about 3 m(e.g., between about 0.25 m and about 1.3 m or between about 0.5 m andabout 0.76 m). Indeed, in some embodiments, the ID (and/or other one ormore other measurements of the reactor core tube) is adjusted orotherwise set to meet the needs of a particular fuel, application,and/or a desired energy output.

The walls of the reactor core tube 120 can be any suitable thickness.Indeed, in some embodiments, the distance between the tube's outerdiameter (OD) and ID (or wall thickness) is between about 0.1 centimeter(cm) and about 1 m, or any thickness that falls in such range. Indeed,in some embodiments, the tube has a wall thickness that falls betweenabout 1 cm and about 13 cm (e.g., between about 1.5 cm and about 3.5cm). In other embodiments, the tube's wall can be any other suitablethickness (e.g., based on energy output needs).

With reference now to the end caps, although some embodiments of thereactor core 70 are formed with one or both ends (e.g., ends 140 and/or145) being closed, in some embodiments, the first and/or second ends ofthe reactor core tube 120 open until they are capped with an end cap.While the end caps can perform any suitable function, in someembodiments, the end caps are configured to retain the fuel in thereactor core and to help direct the fuel into and out of the reactorcore tube.

While the end caps can comprise any suitable component that allows themto perform their desired function, FIG. 4A shows a representativeembodiment in which the first end cap 140 and the second end cap 145each comprises one or more (e.g., 1, 2, 3, 4, 5, 6, or more) fuel ports150. Additionally, while the end caps can be any suitable shape, FIG. 4Ashows an embodiment in which the first 140 and second 145 end caps areflared to respectively help channel fuel from the fuel port 150 in thefirst cap 140 to the internal space 135 of the reactor core tube 120,and then from the internal space 135 of the reactor core tube 120 to thefuel port 150 in the second cap 145.

Where the reactor core 70 comprises a first 140 and/or second 145 endcap (or fuel heads), the end caps can be coupled to the core through anysuitable method. Some example of such methods include, withoutlimitation, being integrally formed with, being threaded together with,via a pressure and/or friction fitted together with, via one or moremating surfaces (e.g., grooves and corresponding ridges or otherwise),via a luer-taper connection, via one or more seals (e.g., carbon seals,carbon rope seals, rubber seals, positive seals, mating seals,nano-composites, and/or other suitable seals), via welding, via one ormore adhesives, via one or more mechanical fasteners (e.g., rivets,clamps, clamping mechanisms, reflectors 75 and/or other objects thathelp press the caps into the reactor core tube 120, screws, bolts,clips, pegs, crimps, pins, brads, threads, brackets, catches, couplers,key-way splines, straps, cramps, heat shrink binding mechanisms, and/orany other suitable mechanical fasteners), and/or other suitablefastening mechanism. Indeed, in some embodiments, the end caps arecoupled to the reactor core tube via a friction fitting, with one ormore seals (e.g., carbon ropes, positive seals, and/or other suitableseals) being disposed between the end caps and the reactor core tube tohelp maintain an air-tight and/or fluid/fuel-tight seal between the capsand the reactor core tube.

As mentioned, in some embodiments, the internal space 135 in the reactorcore tube 120 comprises one or more internal moderators that areconfigured to help the fuel reach (and/or maintain) a critical state inthe reactor core 70. In this regard, the internal moderators cancomprise any suitable component or components that are capable ofperforming the described function. Some examples of suitable internalmoderators include, but are not limited to, one or more rods, balls,pellets, beads, granules, particles, blocks, articles, pipes, graphitegels, gels, pieces, and/or other objects that can be surrounded byand/or filled with the fuel so as to allow the material of the moderator(e.g., carbon, graphite, and/or any other suitable material capable ofbringing the cracked fuel to a critical state) to function as amoderator. Indeed, in some embodiments, the internal moderators comprisegraphite balls, and more particularly substantially pure graphite havinga purity level of about 99% or greater (e.g., having a graphite purityof at least about 99.9%).

In some other examples, the internal moderators comprise one or morecylinders, blocks, wedges, pins, rods, balls, solid block insertsdefining a plurality of holes, the reactor core 70 itself (e.g., whereinthe internal space 135 comprises one or more fuel channels or holesextending through a portion of the reactor core), and/or other suitableobjects that define one or more holes therein, wherein such holes areconfigured to channel the fuel from a first portion (e.g., a first end125 portion, a first diffuser (as discussed below), and/or a first endcap 140) to a second portion (e.g., a second end 130 portion, a seconddiffuser (as discussed below), and/or a second end cap 145) of thereactor core. Indeed, in some embodiments, the reactor core itself actsas the internal moderator. In some other embodiments, however, theinternal moderators comprise one or more fuel pin rods, fuel wedges,and/or graphite spheres.

Where the reactor core 70 itself acts as the internal moderator, thereactor core can comprise any suitable characteristic that allows it tobring and/or maintain the fuel at a critical state. In some embodiments,the core comprises (e.g., by itself and/or houses) a solid block ofmaterial (e.g., graphite, as discussed below) defining one or more fuelchannels. In this regard, the core can comprise any suitable number offuel channels, including, without limitation, between about 1 fuelchannel and about 2,000 fuel channels, or any number of channels fallingwithin such range. Indeed, in some embodiments, the reactor core definesbetween about 3 and about 150 (e.g., between about 3 and about 60 orbetween about 80 and about 130) fuel channels. By way of non-limitingillustration, FIGS. 4B and 4C respectively show some embodiments inwhich the reactor core 70 itself defines 9 and 37 fuel channels 155.Additionally, FIG. 4D illustrates an embodiment in which the reactorcore 70 comprises a cylindrical insert 156 that is disposed within thereactor core tube 120, and which defines 9 fuel channels 155. While thefuel channels 155 shown in FIGS. 4B-4D are shown to be substantiallycircular or cylindrical in shape, the channels can have any othersuitable shape that also the reactor to function, including, withoutlimitation, being tubular, prism shaped, round balls, egg-shaped balls,polygonal balls, and/or any other suitable shape.

Where the reactor core 70 comprises one or more fuel pin rods, the fuelpin rods can comprise any suitable component or characteristic thatallows them to bring a portion of the molten fuel to (and/or to bemaintained at) a critical state. Indeed, while the pins can be anysuitable length, in some embodiments, they are of a sufficient lengththat allows them to direct fuel from the first end 125 to the second end130 of the reactor core tube 120.

Additionally, in some embodiments, the pins define one or more holes, orfuel channels, that extend through a length of the pins to channel thefuel from the reactor core tube's first end 125 to its second end 130.The channels can be disposed in the pins in any suitable manner,including, without limitation, by running substantially parallel with alongitudinal axis running through a length of the pins, by cork-screwingthrough the pins, by twisting through the pins, by extending through thepins at an angle, by rotating though the pins, by spiraling through thepins, by extending through the pins in a serpentine manner, and/or inany other suitable manner. In accordance with some embodiments, however,FIGS. 4A-4E show that the fuel channels 155 (which may also be referredto as internal fuel conduits and holes) run substantially straightthrough the pins 160 (e.g., parallel with the pins' longitudinal axes).

Where the reactor core 70 comprises one or more pins 160, the pins caneach define any suitable number of holes that allow the core to bringand/or maintain the fuel at a critical state. In this regard, each pincan comprise 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, or moreholes. By way of non-limiting illustration FIG. 4F shows an embodimentin which several pins 160 comprise four fuel channels 155, while acenter pin 165 comprises eight fuel channels 155. In some embodiments,each hole in the pin is a fuel channel that extends through the pin. Insome other embodiments, however, even though a pin defines multipleentry and/or exit holes, the holes are in fluid communication with asingle fuel channel that flows through the pin.

The pins 160 can be any suitable shape, including, without limitation,being substantially cylindrical; tubular; cuboidal;rectangular-prism-shaped; triangular-prism-shaped;polygonal-prism-shaped; hexagonal-prism-shaped; pentagonal-prism-shaped;cuboidal-prism- shaped; octagonal-prism-shaped; segment-prism- shaped;parallel-piped-prism-shaped; pill-shaped (e.g., cylindrical with roundedends); having an outer perimeter with a cross-sectional appearanceresembling that of a peanut, cells in anaphase, cells in telophase,and/or a double-barreled shotgun; having a cross-sectional viewresembling 2, 3, 4, 5, 6, or more intersecting circles; having or morecorresponding shapes that fit together to substantially fill a portionof the reactor core 70; and/or any other suitable shape. By way ofnon-limiting illustration, FIGS. 4A and 4F show some embodiments inwhich the pins 160 have a cylindrical shape and/or (in the case of thecenter pin 165 shown in FIGS. 4A and 4F) a cross-sectional viewresembling cells in telophase.

Where the reactor core 70 comprises one or more pins 160, the reactorcore can comprise any suitable number of pins that allows the reactorcore to function as described herein. In this regard, while someembodiments of the core comprise no pins, other embodiments comprisebetween about 1 and about 2,000 pins, or any subrange thereof. Indeed,in some embodiments, the reactor core comprises between about 1 andabout 140 pins, or any subrange thereof (e.g., between about 12 andabout 80 pins). By way of non-limiting illustration, FIG. 4F shows anembodiment in which the reactor core 70 comprises a total of 15 pins (asshown by pins 160 and 165).

Although, in some embodiments, the internal space 135 is mostly (if notentirely) filled with fuel pin rods 160, in other embodiments, inaddition to (or in place of) the pins, the internal space houses one ormore wedges. In this regard, the term wedge may be used to describe anysuitable internal moderator (including, without limitation, a graphiteand/or other suitable moderator) defining one or more fuel channels 155that run through a length of the moderator. In this regard, someembodiments of the described fuel pins may be described as belonging toa sub-class of fuel wedges (especially where the pins define two or morediscrete fuel channels). In some embodiments, however, the term fuelwedge may refer to an elongate, graphite (and/or carbon) moderator thatdefines a plurality of fuel channels that extend along a length of thewedge, wherein the wedge is configured to fit in (and, in someembodiments, to stack or fit together with other wedges and/or pins tosubstantially fill) the internal space. Additionally, while the fuelwedges can have any suitable shape that allows them to act asmoderators, in some embodiments, the wedges have a surface that isconfigured to substantially contour with an inner surface of the reactorcore 70 (e.g., an inner surface of the reactor core tube 120) and/or tocome into contact with such inner surface at more than one place. Forinstance, in some embodiments in which the reactor core tube 120 definesan interior surface having a polygonal, rounded, contoured, and/orirregular surface, an outer surface of one or more fuel wedges isconfigured to substantially contour such interior surface and/or to atleast contact such surface in more than one location at a time.

In this regard, FIG. 4F shows an embodiment in which the reactor coretube 120 defines a interior surface 170 (that is cylindrical, tubular,polygonal, irregular, symmetrical, and/or any other suitable shape), andin which an outer surface 175 of each of the fuel wedges 180 is curved,angled, and/or otherwise configured to substantially correspond in shapewith the interior surface 170 of the reactor core tube 120.

The fuel wedges 180 can have any suitable shape that allows the reactor20 to function as intended. Some non-limiting examples of suitableshapes include that of geometrical sector-shaped prism, an arc-shapedprism, a polygonal prism, a rounded prism, a hexagonal prism, apentagonal prism, a triangular prism, a cuboidal prism, a parallel-pipedprism, a segment prism, a sector prism, a truncated sector prism, anelongated diamond shaped prism, and/or any other suitable shape.

In accordance with some embodiments, however, FIG. 4F (and FIG. 4A)illustrates an embodiment in which the fuel wedges 180 comprise asubstantially wedge-shaped prism 181, having a plurality of rounded,angled, and/or other suitable surfaces 185 that are configured to holdone or more pins (e.g., pins 160 and/or 165). FIG. 4G illustrates anembodiment in which the reactor core 70 comprises multiplesubstantially-sector-shaped wedges 182, having a pin 160 disposedbetween the wedges. In particular, while the reactor core 70 cancomprise any suitable number of wedges (i.e., 1, 2, 3, 4, 5, 6, 7, 8, 9,10, or more) FIG. 4G shows an embodiment in which the core 70 comprisesfour wedges 180. Additionally, FIG. 4H illustrates an embodiment inwhich the wedges 180 are substantially sector-shaped, and wherein thereare no pins disposed within the reactor core 70. Furthermore, FIG. 4Iillustrates an embodiment in which the reactor core 70 comprises aplurality of arc-shaped prism wedges 190 surrounding a plurality ofarc-shaped prism internal moderators 195 and a fuel pin 160. In stillother non-limiting examples, FIGS. 4N-4O show that in some embodiments,the fuel wedges 180 are shaped as prisms having the shape of squareprisms, as prisms resembling segments of a cylinder, as truncated sectorprisms, etc.

Where the reactor core 70 itself, an insert in the core (e.g., thecylindrical insert 156), the pins 160, the wedges 180, and/or one ormore other internal moderators each comprise one or more fuel channels155 that are configured to direct fuel from a first portion (e.g., afirst end 125 portion, a first diffuser (as discussed below), and/or afirst end cap 140) to a second portion (e.g., a second end 130 portion,a second diffuser (as discussed below), and/or a second end cap 145) ofthe reactor core 70, the channels can be any suitable size that allowsthe fuel to flow through the channels. In some embodiments, the holeshave an ID that is between about 0.05 cm and about 60 cm, or any ID thatfalls in such range (e.g., between about 0.5 cm and about 4 cm). Indeed,in some embodiments, the holes in the pins have an ID between about 0.9cm and about 30.5 cm. In other embodiments, the fuel channels have an IDbetween about 0.95 cm and about 23 cm. By way of non-limitingillustration, FIG. 4B illustrates an embodiment in which the reactorcore 70 defines fuel channels 155 that have an ID of about 0.95 cm (±0.9cm). FIG. 4B illustrates an embodiment in which the reactor core 70defines fuel channels 155 of two different sizes, which have an ID ofbetween about 20 cm (±2 cm) and about 12 cm (±2 cm). FIG. 4C, on theother hand, illustrates an embodiment in which the reactor core 70defines fuel channels 155 having an ID of about 7.6 cm (±2 cm). In stillother embodiments, one or more fuel channels in the reactor core have aninner diameter of about 3.8 cm±1 cm.

Although, in some embodiments, the internal moderator or moderators(e.g., the fuel pins 160, fuel wedges 180, cylindrical insert 156,and/or other suitable moderators) are configured to substantially fillthe reactor core 70 when the core is cool, in some embodiments, internalmoderators are sized so as to be slightly smaller than the internalspace 135 of the reactor core tube 120—thus allowing the internalmoderators to expand (as they are heated) to substantially fill theinternal space without expanding so much that they crack or break thereactor core tube.

While the internal moderators can be any suitable size at standardtemperature and pressure (or STP) that allows the reactor 20 to functionas intended, in some embodiments, the volume (and/or length) of all ofthe internal moderators is configured to be between about 0.01% andabout 15%, or any subrange thereof, smaller than the internal volume(and/or diameter or length) of the reactor core tube 120 at STP. Indeed,in some embodiments, the internal moderators (as a whole) have a totalvolume (and/or diameter or length) that is anywhere between about 1% andabout 10% (e.g., between about 2.5% and about 5.5%) smaller than theinternal volume (and/or diameter or length) of the reactor core tube atSTP.

The ends of the internal moderators (e.g., the reactor core 70 itself,the cylindrical insert 156, the fuel pins 160, and/or the fuel wedges180) can have any suitable shape that allows them to be used in thereactor core 70. Indeed, in some embodiments, the ends of the pins,wedges, inserts, etc. are substantially flat; are rounded; include oneor more walls, spacers, seals, protuberances, and/or other standoffsthat are configured to space openings to the various fuel channels 155away from an object (e.g., an end cap 140 or 145, or a diffuser, asdiscussed below); and/or are otherwise shaped to allow the fuel to enterinto one end of, and to exit from an opposite end of, the variousmoderators. By way of non-limiting illustration, FIGS. 4J-4K illustratesome embodiments in which the pins 160 and 165 and the wedges 180 eachcomprise one or more standoffs 200 that are configured to space openingsfor the fuel channels 155 away from an object (e.g., a diffuser 205, thefirst end cap 140, the second end cap 145, and/or any other suitableobject).

Where one or more of the internal moderators (e.g., the fuel pins 160,fuel wedges 180, etc.) comprise one or more standoffs, the standoffs canbe any suitable length. Indeed, in some embodiments, the standoffs at afirst end or second end of the fuel pins, and/or fuel wedges are,individually, any suitable length between about 0.01 cm and about 20 cm,or any subrange thereof. Indeed, in some embodiments, the standoffs atone or both ends of the pins and/or wedges are, at each end, betweenabout 1 cm and about 5 cm. In still other embodiments, the standoffs atone or both ends of the pins and/or wedges are, individually, betweenabout 2 cm and about 4 cm (e.g., about 3.8 cm±0.5 cm). In still otherembodiments, the standoffs are any other suitable length (e.g., based onenergy output needs, fuel flow needs, the size of the reactor core 70,and/or any other suitable factor).

With reference now to the diffusers 205, some embodiments of the reactorcore 70 optionally comprise one or more baffles, channels, meshes,tubing, blocks, and/or any other suitable diffusers that are capable ofdistributing fuel from the first end cap 140 into the fuel channels 155in the pins 160 and/or wedges 180, and/or from the fuel channels in thepins and/or wedges and into the second end cap 145. More particularly,the diffuser can comprise any suitable component (e.g., a manifoldconnected, fuel lines, holes, flutes, and/or any other suitablecharacteristic) that allows the diffuser to direct fuel to one or moreportions of the reactor core (or internal moderator).

Where the reactor core 70 comprises a diffuser 205, the core cancomprise any suitable number of diffusers, including, withoutlimitation, 1, 2, 3, 4, 5, or more diffusers at one or both ends of thecore. Indeed, in some embodiments (as illustrated in FIG. 4J), thereactor 20 comprises one diffuser 205 adjacent to the first end cap andanother diffuser 205 adjacent to the second end cap 145. In some otherembodiments, however (e.g., where the reactor core is used at an inclineand/or vertically), the core comprises one or more diffusers at a bottomend of the core (e.g., adjacent to the first end cap) and does notnecessarily have a diffuser near the top end of the core (e.g., adjacentto the second end cap).

While the diffusers 205 can have any suitable characteristic that allowsthem to function as described herein, in accordance with someembodiments, FIG. 4J shows the diffuser 205 comprises a plate 210 withone or more holes 215, with the plate being disposed between the fuelport 150 of the corresponding end cap (e.g., end caps 140 and/or 145)and the pins 160 and/or wedges 180. Additionally, FIG. 4A shows anembodiment in which the diffusers 205 are formed with the end caps(e.g., end caps 140 and/or 145). In accordance with some otherembodiments, however (and as shown in FIG. 4J), the diffusers 205 areformed separate from the end caps (e.g., end caps 140 and/or 145) so asto be inserted into one of the end caps, sandwiched between an end capand a portion of the reactor core 70, and/or to be placed in any othersuitable location.

Where the reactor core 70 comprises one or more diffusers 205 defining aplurality of holes (see holes 215 in FIG. 4J), any suitable portion ofthe diffusers' surface area define holes that are configured to channelfuel. Indeed, in some embodiments, the area of the holes in a face ofeach diffuser is between about 50% and about 150% (or falls in anysuitable subrange thereof) of the area of the fuel channels 155 in aface of the reactor core and/or the internal moderator. Indeed, in someembodiments, the area of the holes in a face of each diffuser is aboutequal (±10%) to the area of the fuel channels in a face of the reactorcore and/or the internal moderator.

Turning now to the fuel inlets 80 and fuel outlets 85, the reactor 20can comprise any suitable number of fuel inlets and outlets (e.g., 1, 2,3, 4, 5, 6, or more) that allows fuel to pass (selectively and/orotherwise) through one or more fuel ingress ports 151 (or inlets) at afirst end of the reactor (e.g., the first end cap 140) and to then exitthrough one or more fuel egress ports 152 (or outlets) at a second endof the reactor (e.g., the first end cap 145). In one non-limitingillustration, however, FIG. 2B shows an embodiment in which the reactor20 comprises one fuel inlet 80 and one fuel outlet 85. Additionally,while the fuel inlets can be any suitable shape (e.g., circular,polygonal, and/or any other suitable shape), in some embodiments, anegress from the fuel inlet and ingress to the fuel outlet substantiallycorrespond with a shape of a corresponding fuel port 150. Indeed, insome embodiments, in which the fuel ports are substantially circular inshape, the egress from the fuel inlet and the ingress to the fuel outletare also substantially circular in shape.

While the fuel inlets 80 and fuel outlets 85 can be made of any suitablematerials (e.g., graphite, one or more nickel alloys, low-chromiumnickel-molybdenum alloys (such as HASTELLOY-N™), metals, cements,ceramics, synthetic materials, composites, nano-composites, and/or anyother suitable materials), in some embodiments, the fuel inlet andoutlet each comprise a low-chromium nickel-molybdenum alloy (e.g.,HASTELLOY-N™ materials), with one or more seals (e.g., carbon seals,carbon rope seals, composites, and/or other suitable seals) beingdisposed between the inlet and outlet and the corresponding end cap(e.g., the first 140 or second 145 end cap) to which they extend.Indeed, in some embodiments, the fuel inlets 80 and outlets 85 comprisea HASTELLOY-N™ material that is lined with graphite.

With reference now to the reactor control mechanism 90, some embodimentsof the described system 10 are configured to selectively modify the rateat which fuel flows through the reactor core 120. In this regard, insome cases and within some limits, as fuel is forced through the reactorcore 70 at higher and higher rates, the fuel is able to interact withthe internal moderators to allow the fuel to reach higher and highertemperatures. Conversely, in some cases and within some limits, as therate at which fuel flows through the reactor core is slowed, thetemperature of the fuel also drops. Indeed, in some embodiments, if thefuel is allowed to stay stagnant in the reactor core for an extendedperiod of time, the fuel will lose its critical state and will (if leftlong enough) even harden. Thus, by varying the rate at which fuel movesthrough the reactor core, the described system can vary the amount ofheat (and hence the amount of electricity) that the system produces.Moreover, by stopping the flow of fuel through the core, the system canbe permanently and/or temporarily shut down (e.g., by allowing the fuelto cool and harden).

The fuel can flow through the reactor core 70 at any suitable rate thatallows the reactor core to function as described herein. In this regard,the rate at which the fuel flows through the core can be varied based onthe size of the core, the desired amount of heat generated by thereactor core, the amount of fissionable material in the fuel, a desiredhomogeneous balance, and/or a wide variety of other factors. Indeed,while the fuel can flow through the reactor core at absolutely anysuitable rate, in some embodiments, the fuel is configured to flowthrough the core at a rate between about 0 Liters per min (L/min) andabout 45,500 L/min, or within any suitable subrange thereof (e.g., basedon the size, function, and/or any other suitable characteristic of thereactor). Indeed in some embodiments, the fuel is pumped (or otherwisecaused to flow) through the reactor core at a rate between about 0 L/minand about 15,000 L/min, or within any subrange thereof (e.g., betweenabout 19 L/min and about 150 L/min). By way of non-limitingillustration, in some embodiments in which the reactor core has an outerdiameter of about 3 m, with a length of about 4.3 m, and with about 125fuel channels 155 having an inner diameter between about 1.27 cm andabout 6.35 cm (e.g., about 3.81 cm±0.5 cm), the fuel is pumped at (undersome desired operating conditions) a rate of between about 18.9 L/minand about 50 189.3 L/min (e.g., between about 37 L/min and about 133L/min).

Where the described system 10 comprises one or more mechanisms forvarying the rate at which fuel flows through the reactor core 70, thereactor control mechanisms 90 can comprise any suitable component ormechanism that is capable of performing such a function. In this regard,some non-limiting examples of suitable reactor control mechanismsinclude one or more variable frequency fuel pumps, fuel pumps, valves,mechanisms in which the reactor core is rotatable so as to move the fuelports 150 and the corresponding fuel inlet 80 and outlet 85 into and outof alignment with each other, mechanisms that are capable of changing anangle of the reactor core (e.g., to have gravity affect the flow),and/or any other suitable mechanism. Indeed, in at least someembodiments, one or more pumps 22 (as shown in FIG. 1A, see also FIG.3C) are configured to control (e.g., increase, decrease, stop, maintainsubstantially constant, vary, and/or otherwise control) the rate atwhich the fuel flows through the reactor 20. In still other embodiments,in addition to, or in place of, such pumps, the reactor core isconfigured to be rotated to increase and/or decrease the rate at whichfuel passes through the reactor 20.

Where the reactor core 70 is configured to rotate to vary the rate atwhich fuel passes through the reactor 20, the reactor core can berotated in any suitable manner that allows a passage between the fuelinlet 80 and/or outlet 85 and a corresponding fuel port 150 (e.g., inthe first 140 and/or second 145 end cap) to become more and/or lessoccluded as the reactor core rotates (e.g., as one opening is rotatedinto and/or out of alignment with the other). Indeed, in someembodiments, the reactor core is configured to be rotated manuallyand/or automatically (e.g., via one or more computer systems) via thereactor control mechanism 90, which comprises one or more motors,servos, actuators, gear drives, worm drives, kelley drives, and/or othersuitable mechanisms. In this regard, FIG. 2A, 4L, and 4M show someembodiments in which the reactor core 70 is coupled with a partial gear220 (or a sector gear) that is intermeshed with a second gear 225 thatis sealed within the housing 65 and that comprises a pinion, gear,and/or other contact surface 230 (e.g., a hex head, a head with splines,and/or any other suitable surface that can be engaged by a wrench, prybar, motor, servo, pneumatic driver, kelley shaft, drill, and/or othersuitable tool that can be used to turn the contact surface), which canbe used to turn the second gear to rotate the reactor core, to therebyvary the rate at which fuel is moved through the reactor and, hence, theamount of energy that is produced by the system 10. Accordingly, in someembodiments, a user can use a wrench or other turning tool to rotate thecontact surface 230 and hence the reactor core. Thus, even if one ormore pumps go down and/or power is lost, in some embodiments, a user canmanually rotate the reactor core to slow and/or stop fuel flowing thoughthe reactor (e.g., by moving the fuel port 150 (e.g., in the first 140and/or second 145 end cap) out of alignment with the corresponding inlet80 and/or outlet 85.

Additionally, FIGS. 4M and 6A-6D show that in some embodiments, at leastone reflector 75 (e.g., the second reflector 240, as discussed below) isoptionally configured to allow the partial gear 220 and, hence, thereactor core 70 to rotate clockwise and counterclockwise. While thisability to rotate the reactor core in two directions may serve manypurposes, in some embodiments, it allows the reactor core to move backand forth to break any fuel that has solidified and become crustedbetween the core and a reflector.

Where the reactor core 70 is configured to rotate to vary the rate atwhich fuel flows through the reactor 20, the core can be rotated by anysuitable amount that allows the fuel inlet 80 and/or outlet 85 and acorresponding fuel port 150 (e.g., in the first 140 and/or second 145end cap) to be aligned to allow for a maximum flow of fuel through thereactor and to be shifted with respect to each other (e.g., as the corerotates) such that fuel ports are moved out of alignment with thecorresponding inlet and/or outlet to reduce the size of the aperturethrough which the fuel can enter or exit the core. Indeed, in someembodiments, the reactor core is configured to rotate (clockwise and/orcounter clockwise) between about 0.2 degrees and about 180 degrees, orwithin any subrange thereof. Indeed, in some embodiments, the reactorcore can move the fuel ports from being in maximum alignment with thecorresponding inlet and/or outlet to having the inlet and/or outlet becompletely out of alignment with the corresponding fuel port (e.g., tostop fuel from entering and/or exiting the core) when the core isrotated by about 25 degrees or less (less than about 20 degrees). Insome embodiments, however, the core is configured to rotate less than 20degrees (e.g., to stop and/or otherwise vary the flow of the fuelthrough the cell) in either the clockwise and/or the counter clockwisedirection.

Turning now to the reflectors 75, some embodiments of the describedreactor 20 comprise one or more reflectors that are configured toreflect neutrons and/or gamma rays released from the fuel as the fuelmoves through the reactor core 70. As a result, the reflectors may helpthe reactor bring and/or maintain the fuel at a critical state, while(in some embodiments) preventing radiation from escaping from thereactor 20 and harming individuals in proximity to the reactor. In thisregard, the reflectors can comprise any suitable characteristic thatallows them to function as intended.

In one example of a suitable characteristic of the reflectors 75, thereflectors can be any suitable thickness that allows them to function asdescribed herein. Indeed, in at least some embodiments, the reflectorsensure that an outer surface of the reactor core tube 120 and/or eitherof the end caps 140 or 145 is separated from an internal wall of thehousing 65 by between about 2 cm and about 10 m (or any subrangethereof) by a suitable material (e.g., graphite and/or any othersuitable material, as discussed below). Indeed, in some embodiments, thereflectors ensure that an outer surface of the reactor core tube 120and/or either of the end caps 140 or 145 is separated from an internalwall of the housing 65 by between about 20 cm and about 6 m (e.g., about40 cm±10 cm) of reflector material. More specifically, in someembodiments, the reflectors ensure that an outer surface of the reactorcore tube and/or either of the end caps are separated from an internalwall of the housing by at least about 30 cm.

As another example of a suitable characteristic of the reflectors 75,although some embodiments of the reactor core 70 are permanentlyenveloped in a reflector, in other embodiments, the reactor core issurrounded in the reactor housing 65 by one or more reflectors (and/orsections of reflectors) that are configured to be selectively removedand/or replaced. As a result, in some embodiments, if the reactor core,an internal moderator, a reflector, and/or another portion of thereactor 20 breaks, cracks, ages, and/or otherwise becomes damaged, oneor more reflectors can be removed such that the damaged portion of thereactor can be removed, accessed, repaired, and/or replaced. In thisregard, while the reflectors can be assembled in any suitable mannerthat allows them to surround the reactor core, FIGS. 4M, 5A-7C, andFIGS. 2A-2B show that, in some embodiments, the reflectors 75 comprise afirst 235 and second 240 reflector that are configured to fit togetherto encase the reactor core 70 (e.g., as a clam shell), with a third 245and fourth 250 reflector that each flank the first end cap 140 and thesecond end cap 145. Accordingly, in such embodiments, one or morereflectors can be removed and/or replaced relatively easily.

The various components of the reactor core 70 (including, withoutlimitation, the reactor core itself, the reactor core tube 120, thefirst 140 and second 145 end caps, the cylindrical insert 156, the fuelpins 160, the fuel wedges 180, the diffusers 205, the reflectors 75, thepartial gear 220, alignment pins (as discussed below), and/or any othersuitable portion of the reactor core) can be made of any suitablematerial. Some non-limiting examples of such materials include, but arenot limited to, graphite (e.g., substantially pure graphite having apurity level of about 99% or greater (such as a graphite purity of atleast about 99.9%), a boron-free graphite, a pyrolytic graphite, a CGBgrade graphite, and/or any other suitable graphite) and/or any othersuitable material. Indeed, in some embodiments, the reactor core, thereactor core tube, the end caps, the cylindrical insert, the fuel pins,the fuel wedges, the diffusers, the reflectors, the alignment pins,and/or the partial gear each comprise 99.9% pure, boron-free graphite.In some other embodiments, one or more portions of the reactor corecomprise one or more other metals, cements, ceramics, graphite spheres,and/or other suitable materials. For instance, some embodiments of thepartial gear comprise a metal (e.g., a HASTELLOY-N™ alloy) that isplaced on and/or used to form teeth on the gear.

Turning now to the drains 95, some embodiments of the reactor 20optionally comprise one or more drains that are configured to drain(e.g., into a suitable holding tank) fuel: that seeps from the reactorcore 70, that is released when (or if) the reactor core cracks and/orbreaks, that can be drained to cool the reactor if the reactor starts tooverheat, and/or that is otherwise desirable to drain from the reactor.While such drains can comprise any suitable component that allows themto function as intended, in some embodiments, the drains comprise one ormore ball valves, butterfly valves, gate valves, diaphragm valves,and/or other suitable valves comprising one or more suitable ceramicmaterials, metals, alloys, composites, and/or other suitable materials.Indeed, in some embodiments, the drain 95 (as shown in FIGS. 1B-2B)comprises a ceramic ball valve.

With reference now to the heat exchanger 25, in some embodiments of thedescribed system 10, fuel that is brought to the critical state in thereactor core 70 is optionally pumped (or otherwise moved) through thefirst fluid line 40 (which can be any suitable size and length), fromthe reactor 20, through the heat exchanger 25, and then back into thereactor for reheating. In some such embodiments, the heat exchanger isoptionally configured in such a manner that heat from fuel in the firstfluid line is passed to a heat transfer medium running through thesecond fluid line (which can also be any suitable size and length).Accordingly, the described system can heat the heat transfer mediumwithout ever contaminating it with radioactive materials from the fuel.

While the transfer of heat from the first line 40 to the second line 45can be done in any suitable manner and via any suitable known or novelheat transfer device (or heat exchanger), in some embodiments, the firstfluid line is disposed in proximity to the second fluid line (e.g., asshown in FIGS. 8A-8E). Additionally, in some embodiments, in order tobetter pass heat from the first fluid line to the second fluid line,both lines are at least partially submerged in and/or are otherwisesurrounded by the heat transfer medium. Moreover, while the first andsecond fluid lines can run through the heat exchanger 25 in any suitablemanner (by having one run in a top portion of the heat exchanger whilethe other line runs in the bottom portion, by having portions of thelines disposed in close proximity to each other, etc.), in someembodiments, a portion of the first fluid line is configured to bedisposed in a bottom portion of the heat exchanger while a portion ofthe second fluid line is configured to be disposed in an upper portionof the heat exchanger.

With regards to the heat transfer medium, the heat transfer medium cancomprise any suitable material or materials that allow it to safelyabsorb heat from the first fluid line 40 and, in some embodiments, toflow through the second fluid line 45. Some non-limiting examples ofsuitable heat transfer mediums include one or more salts that are freefrom fissionable materials, water, coolants, graphite gels, and/or othersuitable materials. Indeed, in some embodiments, the heat transfermedium comprises one or more salts, which may include, but are notlimited to, potassium nitrate; sodium nitrate; lithium fluoride;beryllium fluoride; a mixture of lithium fluoride and berylliumfluoride; a metal salt mixture of lithium fluoride, sodium fluoride,and/or potassium fluoride; a thermal graphite gel; and/or any othersuitable salt or salts. Indeed, in some embodiments, the heat transfermedium comprises potassium nitrate and/or sodium nitrate. In some otherembodiments, the carrier medium comprises potassium fluoride, sodiumfluoride, and/or a graphite gel.

Where the heat transfer medium comprises more than one ingredient, thevarious ingredients can be present at any suitable concentration in thefuel. Indeed, in some embodiments, at least two of the components of theheat transfer medium are respectively used at a molar ratio betweenabout 100:1 and 1:100, or at any suitable subrange thereof. In thisregard, in some embodiments, the carrier medium respectively comprisespotassium nitrate and sodium nitrate at a molar ratio between about 6:1and about 0.5:1 (e.g., at a ratio of about 1.5:1). In other embodiments,however, the carrier medium comprises potassium nitrate and sodiumnitrate at any molar ratio that is suitable for a desired energy output,thermal fluid, system, and/or other suitable factor.

The first 40 and second 45 fluid lines can be made of any suitablematerials (e.g., one or more nickel alloys, low-chromiumnickel-molybdenum alloys (such as a HASTELLOY-N™ material), metals,cements, ceramics, synthetic materials, composites, nano-metalcomposites, and/or any other suitable materials) that allow the lines tofunction as intended. In some embodiments, however, the lines eachcomprise a low-chromium nickel-molybdenum alloy.

In addition to the aforementioned characteristics, the heat exchanger 25can comprise any other suitable component, including, withoutlimitation, a housing (e.g., a housing comprising one or more of thematerials and components similar to those discussed above with respectto the reactor 20), one or more drains (e.g., drains comprising one ormore of the materials and characteristics similar to those discussedabove with respect to the drain 95), one or more baffles and/orsupports, mixers (e.g., as discussed above with respect to the heater15), pumps, seals (e.g., as discussed above with respect to thereactor), and/or other suitable components. By way of non-limitingillustration, FIGS. 8A-8E show some embodiments in which the heatexchanger 25 comprises one or more supports 255 with openings 260, drain256, housings 265, and seals 270.

With reference now to the steam generator 30, in some optionalembodiments, once the fuel (which has been brought to a critical stateby passing through the reactor core 70) heats the heat transfer mediumin the second fluid line 45 of the heat exchanger 25, the heated heattransfer medium is circulated (e.g., via one or more pumps or otherwise)in the second line from the heat exchanger to the steam generator(and/or any other suitable device that is capable of using heat from thereactor 20 to expand a media such as air, gas, water, etc.), and thenback to the heat exchanger. In some such embodiments, the second line(and/or an object heated thereby) is brought into contact and/or closeproximity with water (and/or another suitable medium), such that heatfrom the heat transfer medium in the second line is able to convert thewater to steam, which can then be used to turn a turbine connected to anelectric generator 35 (which may include any suitable turbine and/orgenerator).

In addition to the aforementioned components, the steam generator 30 cancomprise any other suitable component that allows it to function asintended. Indeed, in some embodiments, the steam generator comprises ahousing (e.g., a housing comprising one or more of the materials andcomponents similar to those discussed above with respect to the reactor20), one or more drains (e.g., drains comprising one or more of thematerials and characteristics similar to those discussed above withrespect to the emergency drain 95), one or more baffles and/or supports,mixers (e.g., as discussed above with respect to the heater 15), pumps,seals (e.g., as discussed above with respect to the reactor), waterinlets, steam outlets, and/or other suitable components. By way ofnon-limiting illustration, FIGS. 9A-9E show some embodiments in whichthe steam generator 30 comprises one or more supports 280 with openings285, drain 290, housings 295, seals 300, water inlets 305, and steamoutlets 310.

The various portions of the described system 10 can be made in anysuitable manner. In this regard, some non-limiting examples of methodsfor making the described reactor core 70 include boring, machining,etching, cutting, drilling, grinding, shaping, plaining, molding,extruding, sanding, lathing, smoothing, buffing, polishing, and/orotherwise forming various pieces of graphite (and/or another suitablematerial) to form one or more pieces of the reactor core (e.g., thereactor core tube 120, end caps 140 and 145, fuel pins 160, fuel wedges180, diffusers 205, reflectors 75, alignment pins (as discussed below),and/or any other suitable parts). Furthermore, the other portions of thedescribed system can be formed in any suitable manner, including,without limitation, via cutting; bending; tapping; dying; sanding;plaining; shaping; molding; extruding; drilling; grinding; buffing;polishing; connecting various pieces with one or more adhesives,mechanical fasteners (e.g., nails, clamps, rivets, staples, clips, pegs,crimps, pins, brads, threads, brackets, etc.), welds, and/or by meltingpieces together; and/or any other suitable method that allows thedescribed system to perform its intended functions.

The described system 10 and its various components can also be used inany suitable manner. Indeed, as previously described, in someembodiments a molten salt fuel source is added to the reactor core 70where it is allowed to go and/or remain at a critical state beforeflowing into the heat exchanger 25 and then being recycled into thereactor core. In some embodiments, however, the described systemcomprises one or more sensors and/or other indicators that allow a userand/or computer system to monitor and/or control (e.g., automaticallyand/or manually) the reactor. Indeed, in some embodiments, the describedsystem is configured to automatically and/or manually (e.g., based onsensor readings, programming, environmental conditions, emergencyconditions, satellite control, and/or any other suitable factor) varyand/or stop the flow of the fuel through the reactor 20.

Indeed, in some embodiments, the described system 10 is configured toautomatically regulate the flow of fuel through the reactor 20 tooptimize the reactor for desired operating parameters. In some otherembodiments, the described system comprises one or more automatic and/ormanual shutoffs that allow fuel to stop its flow through the reactorand/or to be drained from the reactor.

In addition to the aforementioned features, the described system 10 canbe modified in any suitable manner that allows the system to generateheat and/or electricity. In one example, the various components of thedescribed system can be coupled together in any suitable manner (e.g.,via the first fluid line 40, the second fluid line 45, one or moreconnectors, ball valves, valves, and/or in any other suitable manner).By way of non-limiting illustration, FIG. 1B shows an embodiment inwhich the reactor 20 is coupled to the heat generator 25, which (inturn) is coupled to the steam generator, via one or more connectionpoints 315 (e.g., lugs, recesses, mechanical fasteners, hammer pinrocks, catches, etc.) and connectors 320 (e.g., brackets, catches,braces, couplers, ball connections, joints, etc.).

In another example, one or more components of the described system 10are coupled to a common object. In this regard, some examples of suchobjects include, but are not limited to, a trailer (e.g., for a truck),a skid, a platform, a pallet, a train car, a vehicle (e.g., a train,car, truck, tractor, boat, ship, submarine, submergible, airplane,hovercraft, trolley, tank, motorcycle, bus, transports, heavy machinery,machinery, motor home, van, helicopter, military vehicle, space shuttle,drone, UAV, etc.); and/or any other suitable object.

In another example, some embodiments of the reactor core 70 comprise oneor more fuel pins 160 having rounded ends with one or more fuel channels155 running between the two ends. Indeed, in some embodiments, each suchfuel pin comprises a single internal fuel channel. In each of theaforementioned embodiments, the pins can have any suitablecharacteristics that allows the reactor core to bring the fuel to (or tomaintain the fuel at) a critical state. Indeed, in some embodiments, therounded ends comprise one or more threads or other connection mechanismsconfigured to attach the rounded ends to the pin.

The rounded ends of the pins 160 can further comprise any suitablenumber of holes, of any suitable size, that are configured to directfuel into (and/or out of) the fuel channel(s) running in the pin.Indeed, in some embodiments, each of the rounded ends comprises 1, 2, 3,4, 5, or more openings. Moreover, while the openings in the rounded endsof the pin can extend in any suitable manner, in some embodiments, theopenings are disposed at an angle that directs fuel from the openings to(and/or from) the fuel channel in the pin. Furthermore, in someembodiments, a cross-sectional area of all of the openings in a roundedend of a pin are between about 80% and about 120% (or any subrangethereof) of a cross-sectional area of the fuel channel 155 in the pin.In one non-limiting illustration, FIG. 9F shows an embodiment in which afuel pin 160 comprises two rounded ends 161 defining at least oneopening 162, with a fuel channel 155 running through the pin. Again,while the rounded ends 161 can be coupled to the pin 160 in any suitablemanner, FIG. 9F shows that in some embodiments, the end 161 isthreadingly coupled to the pin 160.

In another example, instead of being configured to generate steam, whichis then used to generate heat, in some embodiments, the heat exchanger25 and/or the second fluid line 45 are configured to heat and expandair. In turn, such expanded air can be used to turn a turbine (orotherwise actuate another suitable device) and generate electricity.

In yet another example, instead of generating steam, the heat exchanger25 and/or the second fluid line 45 are used to heat any other suitableobject and/or medium. Indeed, in some embodiments, the heat exchangerand/or second fluid line are used to heat: a body of water (e.g., fordistillation, desalination, evaporation, aquaculture, and/or any othersuitable purpose), a building, a stadium, a neighborhood, an area, air,a complex, an underground reservoir containing fossil fuels, a heattransfer fluid, tar sands, oil shale, a biofuel waste water treatmentplant, and/or any other suitable object and/or material.

In still another example, instead of having the heat exchanger 25 andthe steam generator 30 comprise two discrete components that aredisposed next to each other, in some embodiments, one is contained (atleast partially) within the other. Indeed, in some embodiments, at leasta portion of the heat exchanger is disposed within the steam generator.

In another example of a manner in which the described system 10 can bemodified, in some embodiments, the rate at which fuel is passed throughthe reactor core 70 is controlled by a computer processor (e.g., asdiscussed below in the Representative Operating Environment system).Accordingly, in some embodiments, a computer (e.g., a special-purposecomputer that is configured to regulate the reactor and/or a generalpurpose computer configured to perform the same function) is configuredto increase the flow of fuel through the reactor core when more energyis needed (e.g., during peak hours of electrical consumption), to slowthe flow of fuel through the reactor core when less energy is needed(e.g., during off-peak hours), and/or to shut down the reactor 20 whendesired (e.g., in case of an emergency, maintenance, etc.).

In yet another example, some embodiments of the described reactor 20comprise one or more bearings and/or low friction surfaces that helpallow for the reactor core 70 to rotate with respect to one or morereflectors 75.

In another example of a modification, in some embodiments, one or morecorners, edges, interfaces, and/or other boundaries of any suitablecomponent of the described system 10 (e.g., the reactor core 70) arerounded, arched, chamfered, and/or otherwise shaped to remove stressrisers and to reduce the likelihood of crack formation.

In another example of a modification, in some embodiments, the reactorcore 70 is non-rotatably fixed within the reactor 20. Thus, in some suchembodiments, the flow rate of the fuel through the reactor is controlledvia one or more pumps and/or valves, via changing an orientation of thereactor, and/or in any other suitable manner (besides by rotating thereactor core, as described earlier).

In even another example of a suitable modification, some embodiments ofthe described system 10 comprise one or more condensers that areconfigured to recycle some or all of the steam produced by the steamgenerator 30.

In still another example of a suitable modification, some embodiments ofthe described system 10 are configured to extract one or more materials(e.g., chemicals, composition, mixtures, gases, and/or other desiredmaterials) from the fuel as it cycles through the system. Indeed, insome embodiments (as illustrated by FIG. 10) the described system 10comprises a processing center 325 that is configured to remove isotopes(e.g., medical grade isotopes) and/or other materials that are generatedas the fuel is cycled.

In another example, the described system 10 can comprise any othersuitable component, including, without limitation, a secondarycontainment structure; a tertiary containment structure; a radiatorconfigured to dissipate heat from the reactor core and/or fuel; one ormore dump tanks configured to receive the fuel and/or heat transfermedium; one or more additional reactors 20 used in parallel, series,and/or any other suitable manner with the first reactor core 70; one ormore emergency programs that are configured to automatically slow and/orstop the flow of fuel through the reactor core; one or more othercomponents and/or programs that are configured to shut in and/or to dumpthe fuel from the reactor core 70; and/or any other suitable component.

In another example of a suitable modification, some embodiments of thedescribed system 10 comprise one or more holding devices, such as thevessel 98 shown in FIG. 1A and/or the heater 15, that are configured tostore fuel prior to its introduction into the reactor core 70.Accordingly, in some embodiments, after the fuel has passed through theheat exchanger 25 and/or the heater 15, the fuel is optionally pumpedrelatively rapidly to the holding device.

Where the system 10 comprises a holding device (e.g., vessel 98), theholding device can comprise any suitable characteristic that allows itto hold the fuel prior to introduction into the reactor core. Indeed, insome embodiments, the holding device comprises one or more reflectors75, a tank that is configured to hold the fuel, one or more heaters(e.g., as discussed above with respect to the heater 15) to keep thefuel at or above a desired temperature, insulation, shielding, and/orany other suitable component or characteristic that allows the holdingdevice to function as described herein.

In yet another example of a suitable modification, one or morecomponents of the described system 10 are optionally coated withgraphite, which may include, but is not limited to, graphite foam,graphite sheets, graphite plates, and/or any other suitable form ofgraphite that can be applied to such components. Indeed, in someembodiments, the container 100, one or more fluid lines 40, the heatexchanger 25, and/or any other suitable component of the system iscoated and/or lined with graphite foam. In such embodiments, thegraphite foam can have any suitable characteristic. For instance, thegraphite foam can be any suitable thickness, including, withoutlimitation, one or more layers of foam having a thickness between about0.1 cm and about 60 cm or in any subrange thereof (e.g., between about 6cm and about 18 cm thick).

In even another example, some embodiments of the reactor 20 are disposedon a supporting surface, such as a foundation, a scaffold, a trailer, atrain track, a boom, a pivoting table, floating river and ocean barges,and/or any other surface that is configured to support the reactor core70 and/or the other components of the reactor. While such a support isconfigured to hold the reactor, in some embodiments, the support furtherstrengthens the reactor to reduce deformation of the core under hightemperatures, inclement weather, earthquakes and/or other acts ofnature, due to gravity, and/or similar forces.

In still another example of a suitable modification, as the reactor coretube 120 (and hence the reactor 20 and reactor core 70) can be anysuitable length (as discussed earlier), in some embodiments, at leastone component of the reactor comprise multiple pieces (or sections ofthe component) that are coupled together to form the component (e.g., arelatively long component and/or a portion of the component). Indeed, insome embodiments, one or more fuel wedges 180 in the reactor comprisetwo or more wedge sections that are placed end to end (or side to side,face to face, and/or are otherwise configured) to form a single wedge.Similarly, in some embodiments, the reflectors 75, the reactor coretube, the container 100, the cover 105, and/or any other suitableportion of the reactor respectively comprises two or more reflectorsections, reactor core tube sections, container sections, coversections, and/or other sections that are attached end to end (or side toside, face to face, and/or in any other suitable manner).

Where one or more components of the reactor 20 comprise multiplesections that couple together to form a complete component (or at leasta larger portion of the component), such components can provide someembodiments of the reactor core with one or more desirablecharacteristics. Indeed, in some embodiments, it is easier and/or lessexpensive to form a relatively long component of the reactor (e.g., afuel wedge 180) out of shorter sections that couple together to form thefull component than it is to simply form the full component as amonolithic object. For instance, in some embodiments, it is easier toform fuel channels 155 (e.g., with desired paths through the wedges,with desired spacing between channels, with inlets that correspondspatially with the corresponding outlets, and/or having any othersuitable characteristic) through multiple short sections than it is toform such channels through a single long fuel wedge. As an additionalbenefit, in some embodiments in which a component of the reactorcomprises multiple sections and one section becomes damaged, it can beeasier and/or less expensive to replace that section than it would be toreplace the entire component (e.g., if the component were formed as asingle piece).

Where one or more components of the reactor 20 comprise multiplesections that couple together (e.g., end to end and/or otherwise) toform a full-length (and/or full-sized) component (and/or portion of thecomponent), the sections of the various components (e.g., the fuel wedge180, the reactor core tube 120, the reflectors 75, and/or any othersuitable component) can be virtually any suitable length that allows thereactor to function. In this regard, while component length will, insome embodiments, vary depending on reactor size, reactor configuration,and/or any other desired characteristic of the reactor, in someembodiments, a section of a fuel wedge (and/or any other suitablecomponent of the reactor, including, without limitation, the reactorcore tube, the reflectors, the container 100, etc.) is between about 1cm and about 20 m in length, or any length that falls therein. Indeed,in some embodiments, a section of the fuel wedge is between about 0.3 mand about 3 m (e.g., between about 0.6 m and about 1.9 m). Thus, by wayof non-limiting illustration, where an embodiment of a full-length fuelwedge is about 7 m, and each section is about 1 m long, the full-lengthwedge comprises seven sections coupled end to end. Again, however,lengths of various component sections may be longer or shorter thanthose described herein, based on a variety of factors, including,without limitation, manufacturing techniques, use conditions, andfactors discussed above.

Where one or more components of the reactor 20 comprises multiplesections that couple together end to end (or in any other suitablemanner) to form a full-length component (and/or a larger portion of thecomponent), the various sections can be coupled together in any suitablemanner that allows the reactor to function. Indeed, in some embodiments,multiple component sections (e.g., multiple fuel wedge 180 sectionsand/or sections of any other suitable component) couple together to forma component (e.g., a fuel wedge) via one or more alignment pins thatextend between two or more sections; one or more processes that extendfrom one section into corresponding recesses in another section;dovetail couplings; mechanical engagements; by welding the varioussections together; via one or more cramps and/or other pieces ofmaterial that are configured to span a joint between two sections and tofit into a keyed recess in each section to retain the sections together;by one or more mechanical and/or frictional coupling mechanisms; by oneor more threaded engagements; by one or more clamps; by one or moremating engagements; by one or more fasteners; by applying pressure toone or more sections with one or more components of the reactor (e.g.,by having the end caps 140 and 145 force wedge sections together; byhaving the reflectors 75 force sections of the reactor core tube 120together, etc.); and/or in any other suitable manner. In someembodiments, however, one or more sections of a component (e.g., a fuelwedge) of the reactor are coupled together via one or more alignmentpins. By way of non-limiting illustration, FIG. 11A shows an embodimentin which a first 400 and a second 405 sections of a fuel wedge 180 arecoupled together via one or more alignment pins 410 that extend betweenthe two sections.

Where multiple sections of a component of the reactor 20 (e.g., multiplewedge 180 sections, such as 400 and 405 and/or any other suitablecomponents of the reactor) are coupled together via one or morealignment pins, the various sections can be coupled together with anysuitable number of alignment pins, including, without limitation, 1, 2,3, 4, 5, 6, 7, 8, 9, 10, 11, 12, or more. By way of non-limitingillustration, FIGS. 11B-11C show some embodiments in which the first 400and second 405 sections of the fuel wedge 180 are configured to coupletogether via two alignment pins 410 that extend into recesses 415 ineach section. Thus, in some such embodiments in which the reactor 20comprises four full-length wedges where each full-length wedge comprisestwo sections joined together, eight alignment pins (e.g., two betweeneach of the two corresponding sections) are used to couple the eightsections together to form the four full-length wedges.

Where the reactor 20 comprises a component (e.g., a fuel wedge 180and/or any other suitable component) that comprises two or more sections(e.g., sections 400 and 405) that are coupled together by one or morealignment pins 410, the alignment pins can be disposed in any suitablelocation that allows the reactor to function. Indeed, in someembodiments in which the fuel wedge is formed by coupling two or morewedge sections together, one or more pins are disposed in and extendfrom an end face (e.g., end face 417); are disposed in and extend from aside interface (e.g., side interface 418 and/or 419); are disposed in anend face towards a medial (e.g., portion 420), lateral (e.g., lateralportion 425), and/or interface 418 and/or 419 portion of the wedge;and/or are disposed in an any other suitable location. By way ofnon-limiting illustration, FIG. 11B shows an embodiment in which thealignment pins 410 and recesses 415 are disposed in an end face 418 andnear a lateral edge 425 of the wedge section 400.

The alignment pins 410 can have any suitable characteristic that allowsthem to couple two or more sections of a component (e.g., a fuel wedge180, a reflector 75, and/or any other suitable component) togetherand/or to maintain such sections in proper alignment with each other(e.g., such that a first fuel channel 156 of first section 400 of a fuelwedge properly aligns with a corresponding second fuel channel 157 of asecond corresponding section 405 of the fuel wedge, as (for example)shown in FIG. 11A). Indeed, the alignment pins can be any suitableshape, including, without limitation, being substantially cylindrical,prism-shaped, slat shaped, corkscrew shaped, bar-shaped, graphite bars,tubular, and/or any other suitable shape that allows them to join and/oralign two sections of a reactor component. By way of non-limitingillustration, FIGS. 11A-11C show some embodiments in which the alignmentpins 410 are substantially cylindrical in shape.

The alignment pins 410 can be any suitable size that allows them tofunction as described herein. In this regard, the alignment pins' sizecan vary based on the size of the reactor 20, the size of the reactorcomponent sections being joined by the alignment pins, and/or any othersuitable characteristic of the reactor. In some embodiments, however,the alignment pins have a length that is between about 1.2 cm and about1.8 m, or in any subrange thereof (e.g., between about 10 and about 45cm). Indeed, in some embodiments, the alignment pins have a length thatis between about 15 cm and about 35 cm (e.g., about 30 cm±2 cm).

While the alignment pins 410 can have any suitable width or diameterthat allows them to function as described herein, in some embodiments,the alignment pins have a width or diameter that is between about 0.5 cmand about 35 cm, or in any subrange thereof. Indeed, in someembodiments, the alignment pins have a diameter/width that is betweenabout 2.5 cm and about 13 cm (e.g., between about 5 cm and about 10.2cm). For instance, some embodiments of the alignment pins have adiameter between about 6.3 cm and about 8.9 cm.

The alignment pins 410 can comprise any suitable material that allowsthem to function as described herein while allowing the reactor 20 tofunction. Some examples of suitable materials include, but are notlimited to, one or more types of graphite, ceramic material, metal,metal alloy (e.g., one or more nickel alloys, low-chromiumnickel-molybdenum alloys (such as HASTELLOY-N™)), cement, stone,synthetic material, and/or any other suitable material. In someembodiments, however (and as discussed above), the alignment pinscomprise graphite.

In some embodiments in which one or more components of the reactor 20comprise multiple sections that couple together to form a largercomponent, such sections are configured to be at least partially sealedtogether. In this regard, the various sections can be sealed together inany suitable manner that provides at least a partial fuel seal betweenthe sections and that allows the reactor to function. Some non-limitingexamples of suitable seals comprise one or more positive seals, carbonseals, carbon rope seals, rubber seals, lip seals, mating seals,compression seals, nano-composites, composites, and/or other suitablesealing mechanisms. In some embodiments, however, the seal comprises apositive seal in which one section of a component (e.g., a first sectionof a fuel wedge 180 and/or any other section of any suitable component)comprises one or more processes that extend from the section and thatare configured to extend into one or more corresponding grooves, slots,and/or other recesses in a corresponding component section. By way ofnon-limiting illustration, FIGS. 11A-11C show some embodiments in whichthe first section 400 of the fuel wedge 180 defines a seal recess 435that is configured to receive a seal projection 440 (e.g., comprisinggraphite and/or any other suitable material) that extends from thesecond section 405 to form a seal between the first and second sections(e.g., to prevent fuel from escaping, and/or reduce the amount of fuelthat escapes, from the wedge).

Although FIGS. 11A-11C show some embodiments in which a seal 445 thatcomprises a semicircular recess 446 receives a semicircular ridge 447,the various portions of the seal can have any suitable shape that allowsthe seal to prevent at least some fuel from leaking past the seal. Inthis regard, some non-limiting examples of seal shapes include one ormore triangular recesses that receive one or more triangular ridges, oneor more square-shaped recesses that are configured to receive one ormore square-shaped ridges, and/or any other suitable shape. By way ofnon-limiting illustration, FIG. 11D shows an embodiment in which theseal 445 comprises a mortise shaped recess 450 and a tenon shaped ridge455; FIG. 11E shows an embodiment in which the seal 445 comprises twomating S-curve surfaces 460; and FIG. 11F shows an embodiment in whichthe seal 445 comprises multiple mating notches 465.

Where one or more seals 445 are disposed between two or more sections ofa component of the reactor 20 (e.g., between wedge sections and/orsections of any other suitable component), the seals can be disposed inany suitable location. Indeed, in some embodiments and as shown in FIGS.11A-11G, the seal 445 is disposed at an end face of a reactor component,namely at an end face 417 of a wedge section (400 or 405). Accordingly,in some embodiments in which two wedge sections are abutted face toface, fuel is able to follow directly from a fuel channel in one sectioninto a corresponding fuel channel in a second section without leakingout of the wedge 180 and/or becoming disposed between the wedge and theinterior surface 170 of the reactor core tube 120.

In addition to or in place of having one or more seals 445 at an endface (e.g., wedge face 417), in some embodiments, one or more seals aredisposed between and along sides of reactor components of the reactor.By way of non-limiting illustration, FIG. 11I shows an embodiment whichthe seal 445 is disposed between side interfaces 418 and 419 of thewedges 180.

Regardless of where the seal 445 located, the seal can extend around anysuitable portion of the rector 20 components. In this regard, FIG. 11Gshows an embodiment in which the seal 445 extends around an outerperimeter 470 of an end face 417 of a wedge section 400. In contrast,FIG. 11H shows an embodiment in which the seal 445 extends around anentire perimeter of each wedge 180.

Where one or more components of the reactor 20 comprise multiplesections that are sealing coupled together, any suitable portion of suchcomponents and any suitable combination of the reactor's components canbe comprise multiple sections that are sealing coupled together. Indeed,FIG. 11J shows that, in some embodiments, the reactor core tube 120comprises 2, 3, 4, or more sections (e.g., sections 121, 122, 123, 124,etc.) that are connected at seams 126 and that house one or more wedges180 (shown in FIG. 11J to be divided by horizontal line 404). In somesuch embodiments, while each wedge can comprise a single monolithicobject, FIG. 11J shows an embodiment in which each of the wedges 180comprise multiple wedge sections (e.g., sections 400, 405, 406, 407,408, 409, etc.) that are coupled together at seams 411. Additionally,FIG. 11J shows an embodiment in which the reflectors (e.g., the first230 and second 235 reflector) comprise multiple sections (e.g., sections231-234 and 236-239) that meet at seams 241. While the seams for thevarious components (e.g., the wedges, the reactor tube, the reflectors,etc.) can be aligned with each other, FIG. 11J shows that, in someembodiments, one or more of the seams (e.g., 126, 241, and 411) of thevarious components are offset from each other to prevent undesiredleakage in the reactor 20.

In accordance with some embodiments, FIG. 11K shows that while thewedges 180 each comprise multiple sections (e.g., sections 400, 405,406, and 407), the reactor core tube 120 comprises a monolithic objectthat houses the wedges 180. Indeed, in some cases, it is easier to makea full-length, monolithic reactor tube defining a single internal spacethan it may be to make a full-length wedge defining a plurality of fuelchannels 155 that extend from a first to a second end of the wedge.Accordingly, by using a monolithic reactor tube with wedges comprisingmultiple sections, in some embodiments, the reactor can be relativelyinexpensive to manufacture. Additionally, in some such embodiments, byhaving some components of the reactor be made up of smaller sections,the reactor can be larger that it could otherwise be. Indeed, in someembodiments, the reactor can be relatively long (as discussed above),giving it (e.g., the reactor core tube) the appearance of a pipeline andthe ability to produce a relatively large amount of heat and/orelectricity.

In addition to the aforementioned features, the described system 10 cancomprise any other suitable feature. Indeed, some embodiments of thedescribed reactor core 70 are configured to be used in any orientation,including, without limitation, in a horizontal, vertical, diagonal,and/or variable orientation. Indeed, unlike some reactors, someembodiments of the described reactor core are configured to be used in ahorizontal orientation (e.g., as shown in FIG. 1C).

In some embodiments, the reactor 20 is configured to function when thereactor (e.g., the reactor core tube 120) is at an angle. Indeed, insome embodiments, by having the reactor tube slope down from the fluidinlet 80 to the fluid outlet 85, gravity helps to pull fuel through thefuel channels 155, which can be especially helpful when the fuelchannels have a relatively small inner diameter and/or are relativelylong. In contrast, by angling the reactor core to slope up from thefluid inlet to the fluid outlet, the core can use gravity to slow theflow of the fuel through the reactor and/or to increase the dwell timeof the fuel within the core.

Where the reactor core tube 120 is disposed at an angle, the tube can bedisposed at any suitable angle. Indeed, in some embodiments, the reactorcore is disposed at an incline or decline between about 0 degrees andabout 90 degrees (or any subrange thereof) with respect to a horizontalplane (e.g., a floor or other horizontal supporting surface). Indeed, insome embodiments, the reactor tube is disposed at an angle Θ (e.g.,sloping from the tube's first end 125 to its second end 130) betweenabout 0 degrees and about 45 degrees (e.g., between about 8 degrees andabout 15 degrees).

In some embodiments, the reactor 20 is configured to function as itsorientation is changed (e.g., from vertical orientation, to diagonalorientation, and/or to a vertical orientation). Accordingly, someembodiments of the described reactor core are well suited forsubmarines, aircraft, and/other moving objects which may slightly orsignificantly vary the orientation of the reactor core.

Additionally, in some embodiments, the reactor 20 is coupled to a devicethat is configured to change an angle of the reactor to vary a flow rateof fuel through the reactor. In this regard, the angle of the reactorcan be changed in any suitable manner, including, without limitation, bybeing automatically done by a computer (e.g., based on a feedback loop,programming, user commands, and/or any other suitable factor), manually,via any suitable machinery (e.g., one or more hydraulic lifts, motorizedlifts, servos, cranes, jacks, pivoting platforms, and/or other suitablemachinery), and/or in any other suitable manner.

As another example of a feature of the described system 10, someembodiments of the system are configured to drain out some or all of thefuel in the reactor core 70 to shut down the reactor 20. Indeed, in someembodiments, the system is configured to allow a significant portion ofthe fuel to be drained from the reactor core (e.g., via the fuel outlet85) such that the remaining fuel in the reactor cools down andsolidifies. In some such embodiments, the reactor can be restarted bycracking the fuel (e.g., via the heater 15), introducing the crackedfuel into the reactor, and then recirculating the cracked fuel until thesolidified fuel in the core is heated and brought to a critical state.

As still another example, unlike some nuclear power plants that requirea relatively large amount of real estate, some embodiments of thedescribed system 10 have a relatively small footprint. Indeed, asdiscussed above, some embodiments of the described system can fit on atrailer, a train car, and/or in a variety of other locations that arerelatively small.

In yet another example, unlike some nuclear reactors that require thereactor core to be shielded by thick magnetic cement, the reflectors 75and the container 100 of some embodiments of the described reactor 20control gamma radiation and neutronic escape sufficiently thatadditional cement shielding is unnecessary.

In still another example, some embodiments of the described system 10are configured to actually use or “burn” nuclear waste from othernuclear reactors. As a result, in some embodiments, the describedsystems are quite beneficial for the environment and relativelyinexpensive to operate.

In still another example of a feature of the described system 10, insome embodiments, as the various components of the fuel are mixed, suchcomponents become polluted from their pure state—thus making themrelatively undesirable to terrorists or others who may seek to createweapons from such materials.

In still another example, some embodiments of the described system 10are configured to produce relatively small amounts of plutonium incomparison to other nuclear power plants.

In even another example, some embodiments of the described reactor core20 are configured to function in zero gravity—making such embodimentsuseful in space.

In yet other examples of features associated with the described system,the reactor 20, in some embodiments of the described system, isconfigured to be air cooled, and to thus require rather small amounts ofwater when compared with some conventional nuclear power reactors.

In even another example of a feature, some embodiments of the describedsystem 10 comprise a reactor core 70 that has an internal space 135 thatis relatively full with internal moderators. In this regard, some suchembodiments leave relatively little room for gas (e.g., hydrogen, and/orother gases) to build-up in the reactor core 70. As a result, in someembodiments, some gases are prevented from forming and/or some gases arereadily purged from the reactor core, thus reducing the chances ofunwanted chemical reactions and/or explosions.

In yet another example, some embodiments of the described system arereadily made mobile, thus making them ideal for power and/or heatgeneration in locations with relatively little infrastructure (e.g., atoil drilling sites, offshore oil drilling platforms, off-planetlocations, the theater of war, water desalination at a body of water,oil spill cleanup, on the moon and/or mars, etc.).

Representative Operating Environment

As mentioned, some embodiments of the described system 10 are configuredto be operated (at least in part) by one or more special-purposecomputers (e.g., computers configured to control the reactor core 70)and/or general purpose computers. Indeed, the described systems andmethods can be used with or in any suitable operating environment and/orsoftware. In this regard, FIG. 12 and the corresponding discussion areintended to provide a general description of a suitable operatingenvironment in accordance with some embodiments of the described systemsand methods. As will be further discussed below, some embodimentsembrace the use of one or more processing (including, withoutlimitation, micro-processing) units in a variety of customizableenterprise configurations, including in a networked configuration, whichmay also include any suitable cloud-based service, such as a platform asa service or software as a service.

Some embodiments of the described systems and methods embrace one ormore computer readable media, wherein each medium may be configured toinclude or includes thereon data or computer executable instructions formanipulating data. The computer executable instructions include datastructures, objects, programs, routines, or other program modules thatmay be accessed by one or more processors, such as one associated with ageneral-purpose processing unit capable of performing various differentfunctions or one associated with a special-purpose processing unitcapable of performing a limited number of functions.

Computer executable instructions cause the one or more processors of theenterprise to perform a particular function or group of functions andare examples of program code means for implementing steps for methods ofprocessing. Furthermore, a particular sequence of the executableinstructions provides an example of corresponding acts that may be usedto implement such steps.

Examples of computer readable media (including non-transitory computerreadable media) include random-access memory (“RAM”), read-only memory(“ROM”), programmable read-only memory (“PROM”), erasable programmableread-only memory (“EPROM”), electrically erasable programmable read-onlymemory (“EEPROM”), compact disk read-only memory (“CD-ROM”), or anyother device or component that is capable of providing data orexecutable instructions that may be accessed by a processing unit.

With reference to FIG. 12, a representative system includes computerdevice 500 (e.g., a monitoring system or other unit), which may be ageneral-purpose or (in accordance with some presently preferredembodiments) special-purpose computer. For example, computer device 500may be a personal computer, a notebook computer, a PDA or otherhand-held device, a workstation, a digital pen, a minicomputer, amainframe, a supercomputer, a multi-processor system, a networkcomputer, a processor-based consumer device, a cellular phone, a tabletcomputer, a smart phone, a feature phone, a smart appliance or device, acontrol system, or the like.

Computer device 500 includes system bus 505, which may be configured toconnect various components thereof and enables data to be exchangedbetween two or more components. System bus 505 may include one of avariety of bus structures including a memory bus or memory controller, aperipheral bus, or a local bus that uses any of a variety of busarchitectures. Typical components connected by system bus 505 includeprocessing system 510 and memory 520. Other components may include oneor more mass storage device interfaces 530, input interfaces 540, outputinterfaces 550, and/or network interfaces 560, each of which will bediscussed below.

Processing system 510 includes one or more processors, such as a centralprocessor and optionally one or more other processors designed toperform a particular function or task. It is typically processing system510 that executes the instructions provided on computer readable media,such as on the memory 520, a magnetic hard disk, a removable magneticdisk, a magnetic cassette, an optical disk, or from a communicationconnection, which may also be viewed as a computer readable medium.

Memory 520 includes one or more computer readable media (including,without limitation, non-transitory computer readable media) that may beconfigured to include or includes thereon data or instructions formanipulating data, and may be accessed by processing system 510 throughsystem bus 505. Memory 520 may include, for example, ROM 522, used topermanently store information, and/or RAM 524, used to temporarily storeinformation. ROM 522 may include a basic input/output system (“BIOS”)having one or more routines that are used to establish communication,such as during start-up of computer device 500. RAM 524 may include oneor more program modules, such as one or more operating systems,application programs, and/or program data.

One or more mass storage device interfaces 530 may be used to connectone or more mass storage devices 532 to the system bus 505. The massstorage devices 532 may be incorporated into or may be peripheral to thecomputer device 500 and allow the computer device 500 to retain largeamounts of data. Optionally, one or more of the mass storage devices 532may be removable from computer device 500. Examples of mass storagedevices include hard disk drives, magnetic disk drives, tape drives,solid state mass storage, and optical disk drives.

Examples of solid state mass storage include flash cards and memorysticks. A mass storage device 532 may read from and/or write to amagnetic hard disk, a removable magnetic disk, a magnetic cassette, anoptical disk, or another computer readable medium. Mass storage devices532 and their corresponding computer readable media provide nonvolatilestorage of data and/or executable instructions that may include one ormore program modules, such as an operating system, one or moreapplication programs, other program modules, or program data. Suchexecutable instructions are examples of program code means forimplementing steps for methods disclosed herein.

One or more input interfaces 540 may be employed to enable a user toenter data (e.g., initial information) and/or instructions to computerdevice 500 through one or more corresponding input devices 542. Examplesof such input devices include a keyboard and/or alternate input devices,such as a digital camera, a sensor, bar code scanner, debit/credit cardreader, signature and/or writing capture device, pin pad, touch screen,mouse, trackball, light pen, stylus, or other pointing device, amicrophone, a joystick, a game pad, a scanner, a camcorder, and/or otherinput devices. Similarly, examples of input interfaces 540 that may beused to connect the input devices 542 to the system bus 505 include aserial port, a parallel port, a game port, a universal serial bus(“USB”), a firewire (IEEE 1394), a wireless receiver, a video adapter,an audio adapter, a parallel port, a wireless transmitter including,without limitation, interface satellite feeds, and/or any other suitableinterface.

One or more output interfaces 550 may be employed to connect one or morecorresponding output devices 552 to system bus 505. Examples of outputdevices include a monitor or display screen, a speaker, a wirelesstransmitter, a printer, and the like. A particular output device 552 maybe integrated with or peripheral to computer device 500. Examples ofoutput interfaces include a video adapter, an audio adapter, a parallelport, and the like.

One or more network interfaces 560 enable computer device 500 toexchange information with one or more local or remote computer devices,illustrated as computer devices 562, via a network 564 that may includeone or more hardwired and/or wireless links. Examples of the networkinterfaces include a network adapter for connection to a local areanetwork (“LAN”) or a modem, a wireless link, or another adapter forconnection to a wide area network (“WAN”), such as the Internet. Thenetwork interface 560 may be incorporated with or be peripheral tocomputer device 500.

In a networked system, accessible program modules or portions thereofmay be stored in a remote memory storage device. Furthermore, in anetworked system computer device 500 may participate in a distributedcomputing environment, where functions or tasks are performed by aplurality networked computer devices. While those skilled in the artwill appreciate that the described systems and methods may be practicedin networked computing environments with many types of computer systemconfigurations, FIG. 13 represents an embodiment of a portion of thedescribed systems in a networked environment that includes clients (565,570, 575, etc.) connected to a server 585 via a network 560. While FIG.13 illustrates an embodiment that includes 3 clients connected to thenetwork, alternative embodiments include at least one client connectedto a network or many clients connected to a network. Moreover,embodiments in accordance with the described systems and methods alsoinclude a multitude of clients throughout the world connected to anetwork, where the network is a wide area network, such as the Internet.Accordingly, in some embodiments, the described systems and methods canallow for remote monitoring, observation, adjusting, and othercontrolling of one or more of the described systems 10 from many placesthroughout the world.

Thus, as discussed herein, embodiments of the present invention embracemolten salt reactors. More particularly, some embodiments of thedescribed invention relate to systems and methods for providing andusing molten salt reactors. While the described systems can include anysuitable component, in some embodiments, they include a graphite reactorcore defining an internal space that houses one or more fuel wedges,where each wedge defines one or more fuel channels that extend from afirst end to a second end of the wedge. In some embodiments, one or moreof the fuel wedges comprise multiple wedge sections that are coupledtogether end to end and/or in any other suitable manner. In some cases,one or more alignment pins also extend between two sections of a fuelwedge to align the sections. In some cases, one or more seals are alsodisposed between two sections of a fuel wedge. Thus, in some cases, thereactor core can be relatively long. Additionally, in some embodiments,one or more sections of the wedges and/or parts of other reactorcomponents are configured to be replaced relatively easily.

The present invention may be embodied in other specific forms withoutdeparting from its spirit or essential characteristics. The describedembodiments, examples, and illustrations are to be considered in allrespects only as illustrative and not restrictive. The scope of theinvention is, therefore, indicated by the appended claims rather than bythe foregoing description. All changes that come within the meaning andrange of equivalency of the claims are to be embraced within theirscope. In addition, as the terms on, disposed on, attached to, connectedto, coupled to, etc. are used herein, one object (e.g., a material,element, structure, member, etc.) can be on, disposed on, attached to,connected to, or coupled to another object—regardless of whether the oneobject is directly on, attached, connected, or coupled to the otherobject, or whether there are one or more intervening objects between theone object and the other object. Also, directions (e.g., front back, ontop of, below, above, top, bottom, side, up, down, under, over, upper,lower, lateral, etc.), if provided, are relative and provided solely byway of example and for ease of illustration and discussion and not byway of limitation. Where reference is made to a list of elements (e.g.,elements a, b, c), such reference is intended to include any one of thelisted elements by itself, any combination of less than all of thelisted elements, and/or a combination of all of the listed elements.Furthermore, as used herein, the terms a, an, and one may each beinterchangeable with the terms at least one and one or more.

What is claimed is:
 1. A method for using a molten salt reactor, themethod comprising: obtaining a molten salt reactor comprising: a tubularreactor core comprising graphite and defining an internal space; and afuel wedge that comprises graphite and defines multiple fuel channels,wherein the fuel wedge is received within the internal space, wherein anouter surface of the fuel wedge comprises a first contoured shape,wherein an internal surface of the internal space comprises a secondcontoured shape, wherein the first contoured shape of the fuel wedgesubstantially corresponds in shape and contacts the second contouredshape of the internal surface of the tubular reactor core as the moltensalt reactor operates, and wherein the fuel channels allow a moltenfissionable fuel to flow from a first end of the fuel wedge to a secondend of the fuel wedge, and flowing the molten fissionable fuel throughthe fuel channels.
 2. The method of claim 1, wherein the tubular reactorcore is disposed within, and is in contact with, a reflector comprisinggraphite.
 3. The method of claim 1, wherein the fuel wedge comprises: afirst section comprising a first portion of the fuel channels; and asecond section comprising a second portion of the fuel channels, whereinthe first section and the second section are disposed end to end withinthe internal space such that the first and second portions of the fuelchannels are aligned so that the fissionable fuel flows from the firstportion to the second portion of the fuel channels during reactoroperation, wherein an alignment pin extends between the first sectionand the second section of the fuel wedge to keep the first and secondportions of the fuel channels aligned end to end, and wherein a sealcomprising graphite is disposed between the first section and the secondsection of the fuel wedge.
 4. The method of claim 2, wherein thereflector is disposed within, and in contact with a metal housing.
 5. Amethod for providing a molten salt reactor, the method comprising:forming a reactor core that comprises graphite and multiple fuelchannels that are configured to allow a molten salt comprising afissionable fuel to flow from a first end to a second end of the reactorcore; forming a reflector that comprises graphite and defines aninternal surface that substantially conforms to, and is in contact with,an external shape and external surface of a portion of the reactor coreas the molten salt reactor operates; and placing the reactor corewithin, and in contact with, the reflector, wherein the reactor corecomprises a tubular reactor core that defines an internal space, whereinthe method further comprises forming a fuel wedge that comprisesgraphite and defines at least some of the fuel channels, and wherein themethod further comprises placing the fuel wedge within the internalspace such that an outermost surface of the fuel wedge contacts andtracks an interior surface of the internal space of the tubular reactorcore.
 6. The method of claim 5, further comprising placing the reflectorand the reactor core in a metal housing such that the metal housingsubstantially envelopes the reflector.
 7. The method of claim 5, furthercomprising joining a first wedge section and a second wedge sectiontogether, end to end, to form the fuel wedge such that the fissionablefuel flows from the first wedge section to the second wedge section asthe molten salt reactor operates.
 8. The method of claim 7, furthercomprising placing an alignment pin between the first wedge section andthe second wedge section to align portions of the fuel channels in thefirst wedge section with portions of the fuel channels in the secondwedge section such that the fissionable fuel flows from the first wedgesection to the second wedge section as the molten salt reactor operates.9. The method of claim 5, wherein the fuel wedge comprises asubstantially sector-shaped prism configuration with an external arcshaped surface of the sector-shaped prism being in contact with andsubstantially following the interior surface of the internal space ofthe tubular reactor core.
 10. The method of claim 5, further comprisingforming the reflector by coupling multiple reflector components togetheraround, and in contact with, the reactor core.
 11. A method forproviding a molten salt reactor, the method comprising: forming areactor core tube comprising graphite and defining an internal space;disposing in the reactor core tube an internal moderator that comprisesgraphite and defines a fuel channel that is configured to allow a moltensalt comprising a fissionable fuel to flow from a first end to a secondend of the reactor core tube; forming a reflector that comprisesgraphite and defines an internal surface that substantially conforms toan external shape and external surface of a portion of the reactor coretube; placing the reactor core tube within the reflector such that theinternal surface of the reflector is in contact with the external shapeand surface of the portion of the reactor core tube:, coupling a firstend cap at a first end of the reactor core tube such that the first endcap is configured to direct the molten salt from a fuel inlet in thefirst end cap to the fuel channel; and coupling a second end cap at asecond end of the reactor core tube such that the second end cap isconfigured to direct the molten salt from the fuel channel to a fueloutlet in the second end cap.
 12. The method of claim 11, furthercomprising placing the reflector, which houses and is in contact withthe reactor core tube, and the internal moderator, which is disposed in,and in contact with, the reactor core tube, within a housing comprisinga nickel alloy such that the housing substantially envelopes thereflector.
 13. The method of claim 11, further comprising obtaining adiffuser plate defining a plurality of holes, wherein the diffuser plateis configured to at least one of (i) diffuse and (ii) direct thefissionable fuel from the fuel inlet of the first end cap towards thefuel channel, and disposing the diffuser plate between a portion of thefirst end cap and a portion of the internal moderator.
 14. The method ofclaim 11, wherein the internal moderator comprises a first, second, andthird fuel wedge that each have a sector-shaped prism configuration,that each define multiple fuel channels, and that each have an externalarc shaped surface of the sector-shaped prism that is in contact withand that substantially follows an interior surface of the internal spaceof the reactor core tube.
 15. The method of claim 14, further comprisingjoining a first fuel wedge section and a second fuel wedge sectiontogether, end to end, to form the first fuel wedge such that thefissionable fuel is able to flow from the first fuel wedge sectionthrough the second fuel wedge section.
 16. The method of claim 15,further comprising placing an alignment pin between the first fuel wedgesection and the second fuel wedge section to keep the fuel channels ofthe first fuel wedge in fluid communication between the first fuel wedgesection and the second fuel wedge section of the first fuel wedge. 17.The method of claim 15, further comprising forming a seal comprisinggraphite between the first and second fuel wedge sections, wherein theseal is configured to retain the fissionable fuel within the first fuelwedge between the first fuel wedge section and the second fuel wedgesection.
 18. The method of claim 14, wherein the method furthercomprises forming a seal between the first and second fuel wedges, alonga length of the first and second fuel wedges.